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Sample records for candle filter safeguard

  1. DEVELOPMENT OF AN ADHESIVE CANDLE FILTER SAFEGUARD DEVICE

    Energy Technology Data Exchange (ETDEWEB)

    John P. Hurley; Ann K. Henderson; Jan W. Nowok; Michael L. Swanson

    2002-01-01

    In order to reach the highest possible efficiencies in a coal-fired turbine-based power system, the turbine should be directly fired with the products of coal conversion. Two main types of systems employ these turbines: those based on pressurized fluidized-bed combustors and those based on integrated gasification combined cycles. In both systems, suspended particulates must be cleaned from the gas stream before it enters the turbine so as to prevent fouling and erosion of the turbine blades. To produce the cleanest gas, barrier filters are being developed and are in use in several facilities. Barrier filters are composed of porous, high-temperature materials that allow the hot gas to pass but collect the particulates on the surface. The three main configurations of the barrier filters are candle, cross-flow, and tube filters. Both candle and tube filters have been tested extensively. They are composed of coarsely porous ceramic that serves as a structural support, overlain with a thin, microporous ceramic layer on the dirty gas side that serves as the primary filter surface. They are highly efficient at removing particulate matter from the gas stream and, because of their ceramic construction, are resistant to gas and ash corrosion. However, ceramics are brittle and individual elements can fail, allowing particulates to pass through the hole left by the filter element and erode the turbine. Preventing all failure of individual ceramic filter elements is not possible at the present state of development of the technology. Therefore, safeguard devices (SGDs) must be employed to prevent the particulates streaming through occasional broken filters from reaching the turbine. However, the SGD must allow for the free passage of gas when it is not activated. Upon breaking of a filter, the SGD must either mechanically close or quickly plug with filter dust to prevent additional dust from reaching the turbine. Production of a dependable rapidly closing autonomous mechanical

  2. DEVELOPMENT OF A CANDLE FILTER FAILURE SAFEGUARD DEVICE

    Energy Technology Data Exchange (ETDEWEB)

    G.J. Bruck; E.E. Smeltzer; Z.N. Sanjana

    2002-06-06

    Development, testing and optimization of advanced metal and ceramic, barrier and fiber safeguard devices (SGDs) is described. Metal barrier devices are found prone to manufacturing defects and premature blinding. Fiber devices are found to be satisfactory if fine fibers are used. Durable alloys are identified for both oxidation and gasification conditions. Ceramic honeycomb SGDs were found to perform as excellent barrier devices. Optimization has shown such devices to be durable. Field testing of ceramic honeycomb SGDs from two different manufacturers is being pursued.

  3. Novel Backup Filter Device for Candle Filters

    Energy Technology Data Exchange (ETDEWEB)

    Bishop, B.; Goldsmith, R.; Dunham, G.; Henderson, A.

    2002-09-18

    The currently preferred means of particulate removal from process or combustion gas generated by advanced coal-based power production processes is filtration with candle filters. However, candle filters have not shown the requisite reliability to be commercially viable for hot gas clean up for either integrated gasifier combined cycle (IGCC) or pressurized fluid bed combustion (PFBC) processes. Even a single candle failure can lead to unacceptable ash breakthrough, which can result in (a) damage to highly sensitive and expensive downstream equipment, (b) unacceptably low system on-stream factor, and (c) unplanned outages. The U.S. Department of Energy (DOE) has recognized the need to have fail-safe devices installed within or downstream from candle filters. In addition to CeraMem, DOE has contracted with Siemens-Westinghouse, the Energy & Environmental Research Center (EERC) at the University of North Dakota, and the Southern Research Institute (SRI) to develop novel fail-safe devices. Siemens-Westinghouse is evaluating honeycomb-based filter devices on the clean-side of the candle filter that can operate up to 870 C. The EERC is developing a highly porous ceramic disk with a sticky yet temperature-stable coating that will trap dust in the event of filter failure. SRI is developing the Full-Flow Mechanical Safeguard Device that provides a positive seal for the candle filter. Operation of the SRI device is triggered by the higher-than-normal gas flow from a broken candle. The CeraMem approach is similar to that of Siemens-Westinghouse and involves the development of honeycomb-based filters that operate on the clean-side of a candle filter. The overall objective of this project is to fabricate and test silicon carbide-based honeycomb failsafe filters for protection of downstream equipment in advanced coal conversion processes. The fail-safe filter, installed directly downstream of a candle filter, should have the capability for stopping essentially all particulate

  4. ADVANCED SECOND GENERATION CERAMIC CANDLE FILTERS

    Energy Technology Data Exchange (ETDEWEB)

    M.A. Alvin

    2002-01-31

    Through sponsorship from the Department of Energy's National Energy Technology Laboratory (DOE/NETL), development and manufacture of advanced second generation candle filters was undertaken in the early 1990's. Efforts were primarily focused on the manufacture of fracture toughened, 1.5 m, continuous fiber ceramic composite (CFCC) and filament wound candle filters by 3M, McDermott, DuPont Lanxide Composites, and Techniweave. In order to demonstrate long-term thermal, chemical, and mechanical stability of the advanced second generation candle filter materials, Siemens Westinghouse initiated high temperature, bench-scale, corrosion testing of 3M's CVI-SiC and DuPont's PRD-66 mini-candles, and DuPont's CFCC SiC-SiC and IF&P Fibrosic{sup TM} coupons under simulated, pressurized fluidized-bed combustion (PFBC) conditions. This effort was followed by an evaluation of the mechanical and filtration performance of the advanced second generation filter elements in Siemens Westinghouse's bench-scale PFBC test facility in Pittsburgh, Pennsylvania. Arrays of 1.4-1.5 m 3M CVI-SiC, DuPont PRD-66, DuPont SiC-SiC, and IF&P Fibrosic{sup TM} candles were subjected to steady state process operating conditions, increased severity thermal transients, and accelerated pulse cycling test campaigns which represented {approx}1760 hours of equivalent filter operating life. Siemens Westinghouse subsequently participated in early material surveillance programs which marked entry of the 3M CVI-SiC and DuPont PRD-66 candle filters in Siemens Westinghouse Advanced Particulate Filtration (APF) system at the American Electric Power (AEP) Tidd Demonstration Plant in Brilliant, Ohio. Siemens Westinghouse then conducted an extended, accelerated life, qualification program, evaluating the performance of the 3M, McDermott, and Techniweave oxide-based CFCC filter elements, modified DuPont PRD-66 elements, and the Blasch, Scapa Cerafil{sup TM}, and Specific Surface monolithic

  5. Properties of ceramic candle filters

    Energy Technology Data Exchange (ETDEWEB)

    Pontius, D.H.

    1995-06-01

    The mechanical integrity of ceramic filter elements is a key issue for hot gas cleanup systems. To meet the demands of the advanced power systems, the filter components must sustain the thermal stresses of normal operations (pulse cleaning), of start-up and shut-down conditions, and of unanticipated process upsets such as excessive ash accumulation without catastrophic failure. They must also survive the various mechanical loads associated with handling and assembly, normal operation, and process upsets. For near-term filter systems, these elements must survive at operating temperatures of 1650{degrees}F for three years.

  6. FILTER COMPONENT ASSESSMENT--CERAMIC CANDLES--

    Energy Technology Data Exchange (ETDEWEB)

    M.A. Alvin

    2004-04-23

    Efforts at Siemens Westinghouse Power Corporation (SWPC) have been focused on development of hot gas filter systems as an enabling technology for advanced coal and biomass-based gas turbine power generation applications. SWPC has been actively involved in the development of advanced filter materials and component configuration, has participated in numerous surveillance programs characterizing the material properties and microstructure of field tested filter elements, and has undertaken extended, accelerated filter life testing programs. This report summarizes the results of SWPC's filter component assessment efforts, identifying the performance and stability of porous monolithic, fiber reinforced, and filament wound ceramic hot gas candle filters, potentially for {ge}3 years of viable pressurized fluidized-bed combustion (PFBC) service operating life.

  7. Nondestructive Evaluation of Ceramic Candle Filters Using Vibration Response

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Roger H. L.; Kiriakidis, Alejandro C.; Peng, Steve W.

    1997-07-01

    This study aims at the development of an effective nondestructive evaluation technique to predict the remaining useful life of a ceramic candle filter during a power plant's annual maintenance shutdown. The objective of the present on-going study is to establish the vibration signatures of ceramic candle filters at varying degradation levels due to different operating hours, and to study the various factors involving the establishment of the signatures.

  8. Three—Dimensional Flow Characteristics in One Ceramic Candle Filter

    Institute of Scientific and Technical Information of China (English)

    TaewonSeo; KihyunKeum; 等

    1999-01-01

    The objective of this study is to characterize the three-dimensional fluid flow in the vessel containing one ceramic candle filter.The three-dimensional governing equations are formulated in this study and the turbulent κ-ε model is adopted for the numerical computation.It is found that the viscous force is dominant in the porous region with compared to inertia force.Pressue decreases linearly when the flow passing through the porous medium.When the face velocity is 0.03 m/s,the pressure drop is about 350Pa.It has also been found that the fluid with the spiral motion to be sunk into the filter in the vessel.

  9. Fail Save Shut Off Valve for Filtering Systems Employing Candle Filters

    Science.gov (United States)

    VanOsdol, John

    2006-01-03

    The invention relates to an apparatus that acts as a fail save shut off valve. More specifically, the invention relates to a fail save shut off valve that allows fluid flow during normal operational conditions, but prevents the flow of fluids in the event of system failure upstream that causes over-pressurization. The present invention is particularly well suited for use in conjunction with hot gas filtering systems, which utilize ceramic candle filters. Used in such a hot gas system the present invention stops the flow of hot gas and prevents any particulate laden gas from entering the clean side of the system.

  10. Granular-bed and ceramic candle filters in commercial plants: A comparison

    Energy Technology Data Exchange (ETDEWEB)

    Wilson, K.B.; Haas, J.C.; Eshelman, M.B.

    1993-04-01

    Advanced coal fired power cycles require the removal of coal ash at high temperature and pressure. Granular-bed and ceramic candle filters can be used for this service. Conceptual designs for commercial size applications are made for each type of filter. The filters are incorporated in the design of a Foster Wheeler 450 MWe second generation pressurized fluidized bed combustion plant which contains a pressurized fluidized combustor and carbonizer. In a second application, the inters are incorporated in the design of a 100 MWe KRW (air) gasifier based power plant. The candle filter design is state of the art as determined from the open literature with an effort to minimize the cost. The granular-bed filter design is based on test work performed at high temperature and low pressure, tests at New York University performed at high pressure and temperate, and new analysis used to simplify the scale up of the filter and reduce overall cost. The incorporation of chemically reactive granites in the granular-bed filter for the removal of additional coal derived contaminants such as alkali or sulfur is considered. The conceptual designs of the granular-bed inter and the ceramic candle filter are compared in terms of the cost of electricity, capital cost, and operating and maintenance costs for each application.

  11. DEVELOPMENT AND UTILIZATION OF TEST FACILITY FOR THE STUDY OF CANDLE FILTER SURFACE REGENERATION

    Energy Technology Data Exchange (ETDEWEB)

    Bruce S. Kang; Eric K. Johnson

    2003-07-14

    Hot gas particulate filtration is a basic component in advanced power generation systems such as Integrated Gasification Combined Cycle (IGCC) and Pressurized Fluidized Bed Combustion (PFBC). These systems require effective particulate removal to protect the downstream gas turbine and also to meet environmental emission requirements. The ceramic barrier filter is one of the options for hot gas filtration. Hot gases flow through ceramic candle filters leaving ash deposited on the outer surface of the filter. A process known as surface regeneration removes the deposited ash periodically by using a high pressure pulse of gas to back flush the filter. After this cleaning process has been completed there may be some residual ash on the filter surface. This residual ash may grow and this may then lead to mechanical failure of the filter. A Room Temperature Test Facility (RTTF) and a High Temperature Test Facility (HTTF) were built to investigate the ash characteristics during surface regeneration at room and selected high temperatures. The RTTF system was used to gain experience with the selected instrumentation and develop an operating procedure to be used later at elevated temperatures. The HTTF system is capable of conducting surface regeneration tests of a single candle filter at temperatures up to 1500 F. In order to obtain sequential digital images of ash particle distribution during the surface regeneration process, a high resolution, high speed image acquisition system was integrated into the HTTF system. The regeneration pressure and the transient pressure difference between the inside of the candle filter and the chamber during regeneration were measured using a high speed PC data acquisition system. The control variables for the high temperature regeneration tests were (1) face velocity, (2) pressure of the back pulse, and (3) cyclic ash built-up time. Coal ash sample obtained from the Power System Development Facility (PSDF) at Wilsonville, AL was used at the

  12. Pulse cleaning flow models and numerical computation of candle ceramic filters

    Institute of Scientific and Technical Information of China (English)

    2002-01-01

    Analytical and numerical computed models are developed for reverse pulse cleaning system of candle ceramic filters. A standard turbulent model is demonstrated suitably to the designing computation of reverse pulse cleaning system from the experimental and onedimensional computational result. The computed results can be used to guide the designing of reverse pulse cleaning system, which is optimum Venturi geometry. From the computed results, the general conclusions and the designing methods are obtained.

  13. Filtration and dust cake experiment by ceramic candle filter in high temperature conditions

    Energy Technology Data Exchange (ETDEWEB)

    Chung, J.D.; Hwang, T.W.; Park, S.J. [Hoseo University, Asan (Republic of Korea)

    2003-11-01

    Particulate collection at high temperature and high pressure (HTHP) is important in an advanced coal power generation system not only to improve the thermal efficiency of the system, but also to prevent the gas turbine from erosion and to meet the emission limits of the effluent gas. The specifications for particulate collection in those systems such as Integrated Gasification Combined Cycle (IGCC) and Pressurized Fluidized Bed Combustion (PFBC) require absolutely high collection efficiency and reliability. Advanced cyclone, granular bed filter, electrostatic precipitator, and ceramic filter have been developed for particulate collection in the advanced coal power generation system. However, rigid ceramic filters and granular bed filters among them show the best potential. The problems experienced of these systems on performance, materials, and mechanical design were investigated. Ceramic candle filters have the best potential for IGCC at this moment because they have nearly the highest efficiency compared with other filtering systems and have accumulated many reliable design data from many field experiences. The purpose of this study was to investigate the efficiency of ceramic filters and stability of material against high temperature and longterm operation condition by applying fly ash on the surface of the filter and relation of pressure drop and dust cake thickness. Experimental conditions were 50 hours at 450{sup o}C, 650{sup o}C and 850{sup o}C.

  14. Life cycle of a nanosilver based water candle filter: examining issues of toxicity, risks, challenges and policy implications.

    Science.gov (United States)

    Sarma, Shilpanjali Despande

    2011-02-01

    The present study examines the potential environment, health and safety (EHS) implications of a nanoscale silver based candle filter due to enter the Indian market, by utilizing the Life Cycle approach for analyzing key toxicity issues surrounding its manufacture, use and disposal. PMID:21485815

  15. Image Analysis on Detachment Process of Dust Cake on Ceramic Candle Filter

    Institute of Scientific and Technical Information of China (English)

    姬忠礼; 焦海青; 陈鸿海

    2005-01-01

    Based on the analysis of high-speed video images, the detachment behavior of dust cake from the ceramic candle filter surface during pulse cleaning process is investigated. The influences of the dust cake loading,the reservoir pressure, and the filtration velocity on the cleaning effectiveness are analyzed. Experimental results show that there exists an optimum dust cake thickness for pulse-cleaning process. For thin dust cake, the patchy cleaning exists and the cleaning efficiency is low; if the dust cake is too thick, the pressure drop across the dust cake becomes higher and a higher reservoir pressure may be needed. At the same time there also exists an optimum reservoir pressure for a given filtration condition.

  16. 烛式PVPP过滤机的改进%Improvement of Candle-type PVPP Filter

    Institute of Scientific and Technical Information of China (English)

    姚庆节

    2011-01-01

    Analyse the cause of the losses of the PVPP participate, the paper adopted low-speed, multi-layer propeller agitator instead of frame agitator, using new type distributor, depressing the pressure of the air which used in recovery process and so on. As a result, the losses of the PVPP particulate used in candle-type PVPP filter were depressed with better flit efficiency.%通过分析PVPP颗粒发生损耗的原因,采取低速多层螺旋搅拌桨替换框式搅拌桨、改进进料分配器、降低回收压空压力等方法,达到了降低烛式PVPP过滤机使用中PVPP颗粒损耗的目的,提高了过滤效益.

  17. Study on the Cleaninq Method on Filter Element of Candle Filter%烛式过滤机过滤元件清洗方法研究

    Institute of Scientific and Technical Information of China (English)

    来丽静; 王国良

    2012-01-01

    The chemical cleaning method on filter leaf of the candle filter was studied, single factor and orthogonal design were adopted to research the suitable formula. The result shows that the aqueous sodium hydroxide solution had the relatively satisfactory effect, the opimized formula is, concentration 50 g/L, cleaning temperature 60℃, cleaning time 2 h.%采用化学方法对烛式过滤机滤片的清洗进行研究,通过单因素和正交试验对清洗工艺进行优化,结果表明:NaOH清洗效果较好,其最佳工艺为NaoH浓度50g/L,清洗温度60℃,清洗时间2h。

  18. Gas cleaning, gas conditioning and tar abatement by means of a catalytic filter candle in a biomass fluidized-bed gasifier.

    Science.gov (United States)

    Rapagnà, Sergio; Gallucci, Katia; Di Marcello, Manuela; Matt, Muriel; Nacken, Manfred; Heidenreich, Steffen; Foscolo, Pier Ugo

    2010-09-01

    A bench-scale fluidized-bed biomass gasification plant, operating at atmospheric pressure and temperature within the range 800-820 degrees C, has been used to test an innovative gas cleaning device: a catalytic filter candle fitted into the bed freeboard. This housing of the gas conditioning system within the gasifier itself results in a very compact unit and greatly reduced thermal losses. Long term (22h) tests were performed on the gasifier both with and without the catalytic candle filter, under otherwise identical conditions. Analysis of the product gas for the two cases showed the catalytic filtration to give rise to notable improvements in both gas quality and gas yield: an increase in hydrogen yield of 130% and an overall increase in gas yield of 69% - with corresponding decreases in methane and tar content of 20% and 79%, respectively. HPLC/UV analysis was used to characterize the tar compounds.

  19. Material characterization of the clay bonded silicon carbide candle filters and ash formations in the W-APF system after 500 hours of hot gas filtration at AEP. Appendix to Advanced Particle Filter: Technical progress report No. 11, January--March 1993

    Energy Technology Data Exchange (ETDEWEB)

    Alvin, M.A.

    1993-04-05

    (1) After 500 hours of operation in the pressurized fluidized-bed combustion gas environment, the fibrous outer membrane along the clay bonded silicon carbide Schumacher Dia Schumalith candles remained intact. The fibrous outer membrane did not permit penetration of fines through the filter wall. (2) An approximate 10-15% loss of material strength occurred within the intact candle clay bonded silicon carbide matrix after 500 hours of exposure to the PFBC gas environment. A relatively uniform strength change resulted within the intact candles throughout the vessel (i.e., top to bottom plenums), as well as within the various cluster ring positions (i.e., outer versus inner ring candle filters). A somewhat higher loss of material strength, i.e., 25% was detected in fractured candle segments removed from the W-APF ash hopper. (3) Sulfur which is present in the pressurized fluidized-bed combustion gas system induced phase changes along the surface of the binder which coats the silicon carbide grains in the Schumacher Dia Schumalith candle filter matrix.

  20. New approach to safeguards accounting. [Kalman filter method for detecting continual small losses

    Energy Technology Data Exchange (ETDEWEB)

    Pike, D.H.; Morrison, G.W.

    1977-03-01

    In recent years there has been widespread concern over the problem of nuclear safeguards. Due to the proliferation of nuclear reactors throughout the world, the concern about the loss or diversion of nuclear materials at various points in the fuel cycle has greatly increased. To minimize the possibility of material loss, the nuclear industry relies on physical protection systems and materials accountability procedures at licensed facilities. Present techniques of material accountability rely on double-entry accounting systems. For various reasons, only noisy observations of on-hand inventory are available. Hence one is forced to use statistical techniques in an attempt to detect the existence of missing material. Current practice is to use control charts as the basis for detecting significant material losses. Control charts may aid in detecting large material losses but are insensitive to small quantities of material loss, even if these small losses occur repeatedly over a long period of time. The purpose of this research is to show the feasibility of using linear state estimation theory in nuclear material accountability. The Kalman Filter is used as the state estimation technique. The state vector which consists of on-hand inventory and material losses is estimated recursively.

  1. LEAD IN CANDLE EMISSIONS

    Science.gov (United States)

    The candle-using public should be made aware that the core of candle wicks may contain lead. Used as a stiffening agent to keep the wick out of the molten wax, lead can be emitted as particulate to the air and then deposited on indoor surfaces. To define the problem, 100 sets of ...

  2. Image Analysis on Detachment Process of Dust Cake on Ceramic Candle Filter%陶瓷过滤管表面粉尘层清除过程的图像分析

    Institute of Scientific and Technical Information of China (English)

    姬忠礼; 焦海青; 陈鸿海

    2005-01-01

    Based on the analysis of high-speed video images, the detachment behavior of dust cake from the ceramic candle filter surface during pulse cleaning process is investigated. The influences of the dust cake loading,the reservoir pressure, and the filtration velocity on the cleaning effectiveness are analyzed. Experimental results show that there exists an optimum dust cake thickness for pulse-cleaning process. For thin dust cake, the patchy cleaning exists and the cleaning efficiency is low; if the dust cake is too thick, the pressure drop across the dust cake becomes higher and a higher reservoir pressure may be needed. At the same time there also exists an optimum reservoir pressure for a given filtration condition.

  3. First Candle/SIDS Alliance

    Science.gov (United States)

    ... Blog Buy Form Our Store Blog About FIRST CANDLE PROGRAMS Pregnant and Empowered SPONSORED BY THE BOPPY ... that raise money for research and education. First Candle's Legacy Program can help you set up a ...

  4. 16 CFR 501.7 - Candles.

    Science.gov (United States)

    2010-01-01

    ... 16 Commercial Practices 1 2010-01-01 2010-01-01 false Candles. 501.7 Section 501.7 Commercial... 500 § 501.7 Candles. Tapered candles and irregularly shaped decorative candles which are either hand... extent that diameter of such candles need not be expressed. The requirements of § 500.7 of this...

  5. Safeguards Culture

    Energy Technology Data Exchange (ETDEWEB)

    Frazar, Sarah L.; Mladineo, Stephen V.

    2012-07-01

    The concepts of nuclear safety and security culture are well established; however, a common understanding of safeguards culture is not internationally recognized. Supported by the National Nuclear Security Administration, the authors prepared this report, an analysis of the concept of safeguards culture, and gauged its value to the safeguards community. The authors explored distinctions between safeguards culture, safeguards compliance, and safeguards performance, and evaluated synergies and differences between safeguards culture and safety/security culture. The report concludes with suggested next steps.

  6. Ear Candling: A Dangerous Pleasure?

    Directory of Open Access Journals (Sweden)

    Kianoosh Nahid

    2011-01-01

    Full Text Available Ear candling is an alternative medicine practice alleged to enhance general health by putting an end of a hollow candle in the ear canal and lighting up the other end of it. It also is advertised for cerumen and debris (bacteria and fungi removal. Ear candling is claimed to create negative pressure for drawing cerumen from the ear and to benefit the ears in many ways. It is however not free of complications and is now banned. Here we would like to highlight potential complications to this.

  7. When a Standard Candle Flickers

    DEFF Research Database (Denmark)

    Wilson-Hodge, Colleen A; Cherry, Michael L; Case, Gary L;

    2011-01-01

    The Crab Nebula is the only hard X-ray source in the sky that is both bright enough and steady enough to be easily used as a standard candle. As a result, it has been used as a normalization standard by most X-ray/gamma-ray telescopes. Although small-scale variations in the nebula are well known,...

  8. Ear Candling: A Dangerous Pleasure?

    Directory of Open Access Journals (Sweden)

    Kianoosh Nahid

    2011-01-01

    Ear candling is claimed to create negative pressure for drawing cerumen from the ear and to benefit the ears in many ways. It is however not free of complications and is now banned. Here we would like to highlight potential complications to this.

  9. Lighting that One Little Candle.

    Science.gov (United States)

    Scarnati, James T.; Tice, Craig J.

    1988-01-01

    Describes a lesson in which fifth graders made observations of candles. Discusses the progress of the lesson and the necessity of instructing students in what and how to watch and measure. Stresses that this can be easily accomplished inexpensively with imagination. (CW)

  10. Candle and candle wax containing metathesis and metathesis-like products

    Science.gov (United States)

    Murphy, Timothy A; Tupy, Michael J; Abraham, Timothy W; Shafer, Andy

    2014-04-01

    A wax comprises a metathesis product and/or a product that resembles, at least in part, a product which may be formed from a metathesis reaction. The wax may be used to form articles, for example, candles (container candles, votive candles, and/or a pillar candles), crayons, fire logs, or tarts. The wax commonly includes other components in addition to the metathesis product.

  11. Candle and candle wax containing metathesis and metathesis-like products

    Energy Technology Data Exchange (ETDEWEB)

    Murphy, Timothy A; Tupy, Michael J; Abraham, Timothy W; Shafer, Andy

    2014-12-16

    A wax comprises a metathesis product and/or a product that resembles, at least in part, a product which may be formed from a metathesis reaction. The wax may be used to form articles for example, candles (container candles, votive candles, and/or a pillar candles), crayons, fire logs or tarts. The wax commonly includes other components in addition to the metathesis product.

  12. International safeguards

    International Nuclear Information System (INIS)

    Since the start of the post-war era, international safeguards were considered essential to ensure that nuclear materials should not be diverted to unauthorised uses. In parallel, it was proposed to set up an international atomic energy agency within the United Nations through which international cooperation in nuclear matters would be channelled and controlled. Created in 1957, the IAEA was authorized to administer safeguards in connection with any assistance it provided as well as at the request of Member State and of any party to bilateral or multilateral arrangements in its ambit. Today, there are two international treaties requiring that its parties should accept Agency safeguards unilaterally, the Latin America Tlatelolco Treaty of 1967, and the Treaty on the Non-Proliferation of Nuclear Weapons (NPT), operative since 1970, which requires in particular that non-nuclear weapon states should accept Agency safeguards on its peaceful nuclear activities. Thus while NPT covers peaceful nuclear activities indiscriminately in a country, the Agency's original safeguards system is applied according to specific agreements and to given facilities. A basic conflict has now emerged between commercial interests and the increasing wish that transfer of nuclear equipment and know-how should not result in proliferation of military nuclear capacity; however, serious efforts are currently in progress to ensure universal application of IAEA safeguards and to develop them in step with the uses of nuclear energy. (N.E.A.)

  13. Ceramic fiber filter technology

    Energy Technology Data Exchange (ETDEWEB)

    Holmes, B.L.; Janney, M.A.

    1996-06-01

    Fibrous filters have been used for centuries to protect individuals from dust, disease, smoke, and other gases or particulates. In the 1970s and 1980s ceramic filters were developed for filtration of hot exhaust gases from diesel engines. Tubular, or candle, filters have been made to remove particles from gases in pressurized fluidized-bed combustion and gasification-combined-cycle power plants. Very efficient filtration is necessary in power plants to protect the turbine blades. The limited lifespan of ceramic candle filters has been a major obstacle in their development. The present work is focused on forming fibrous ceramic filters using a papermaking technique. These filters are highly porous and therefore very lightweight. The papermaking process consists of filtering a slurry of ceramic fibers through a steel screen to form paper. Papermaking and the selection of materials will be discussed, as well as preliminary results describing the geometry of papers and relative strengths.

  14. Assessment of ceramic membrane filters

    Energy Technology Data Exchange (ETDEWEB)

    Ahluwalia, R.K.; Geyer, H.K.; Im, K.H. [and others

    1995-08-01

    The objectives of this project include the development of analytical models for evaluating the fluid mechanics of membrane coated, dead-end ceramic filters, and to determine the effects of thermal and thermo-chemical aging on the material properties of emerging ceramic hot gas filters. A honeycomb cordierite monolith with a thin ceramic coating and a rigid candle filter were evaluated.

  15. Low emittance upgrade for CANDLE project

    CERN Document Server

    Zanyan, G S

    2015-01-01

    To improve the performance of CANDLE synchrotron light source and stay competitive with recently proposed low emittance upgrade programs in the world we have developed new low emittance lattices for CANDLE booster and storage ring. These lattices have been designed taking into account the new developments in magnet fabrication technology and the multi-bend achromat concept. The main design considerations, the linear and non-linear beam dynamics aspects of the modified lattices are presented.

  16. Reactor safeguards

    CERN Document Server

    Russell, Charles R

    2013-01-01

    Reactor Safeguards provides information for all who are interested in the subject of reactor safeguards. Much of the material is descriptive although some sections are written for the engineer or physicist directly concerned with hazards analysis or site selection problems. The book opens with an introductory chapter on radiation hazards, the construction of nuclear reactors, safety issues, and the operation of nuclear reactors. This is followed by separate chapters that discuss radioactive materials, reactor kinetics, control and safety systems, containment, safety features for water reactor

  17. When A Standard Candle Flickers

    CERN Document Server

    Wilson-Hodge, Colleen A; Baumgartner, Wayne H; Beklen, Elif; Bhat, P Narayana; Briggs, Michael S; Camero-Arranz, Ascension; Case, Gary L; Chaplin, Vandiver; Connaughton, Valerie; Finger, Mark H; Gehrels, Neil; Greiner, Jochen; Jahoda, Keith; Jenke, Peter; Kippen, R Marc; Kouveliotou, Chryssa; Krimm, Hans A; Kuulkers, Erik; Meegan, Charles A; Natalucci, Lorenzo; Paciesas, William S; Preece, Robert; Rodi, James C; Shaposhnikov, Nikolai; Skinner, Gerald K; Swartz, Doug; von Kienlin, Andreas

    2010-01-01

    The Crab Nebula is the only hard X-ray source in the sky that is both bright enough and steady enough to be easily used as a standard candle. As a result, it has been used as a normalization standard by most X-ray/gamma ray telescopes. Although small-scale variations in the nebula are well-known, since the start of science operations of the Fermi Gamma-ray Burst Monitor (GBM) in August 2008, a ~ 7% (70 mcrab) decline has been observed in the overall Crab Nebula flux in the 15 - 50 keV band, measured with the Earth occultation technique. This decline is independently confirmed with three other instruments: the Swift Burst Alert Telescope (Swift/BAT), the Rossi X-ray Timing Explorer Proportional Counter Array (RXTE/PCA), and the INTErnational Gamma-Ray Astrophysics Laboratory Imager on Board INTEGRAL (IBIS). A similar decline is also observed in the ~3 - 15 keV data from the RXTE/PCA and INTEGRAL Joint European Monitor (JEM-X) and in the 50 - 100 keV band with GBM and INTEGRAL/IBIS. Observations from 100 to 500...

  18. When A Standard Candle Flickers

    Science.gov (United States)

    Wilson-Hodge, Colleen A.; Cherry, Michael L.; Case, Gary L.; Baumgartner, Wayne H.; Beklen Elif; Bhat, P. Narayana; Briggs, Michael S.; Camero-Arranz, Ascension; Chaplin, Vandiver; Connaughton, Valerie; Finger, Mark H.; Gehrels, Neil; Greiner, Jochen; Jahoda, Keith; Jenke, Peter; Kippen, R. Marc; Kouveliotou, Chryssa; Krimm, Hans A.; Kuulkers, Erik; Lund, Niels; Meegan, Charles A.; Natalucci, Lorenzo; Paciesas, William S.; Preece, Robert; Rodi, James C.

    2011-01-01

    The Crab Nebula is the only hard X-ray source in the sky that is both bright enough and steady enough to be easily used as a standard candle. As a result, it has been used as a normalization standard by most X-ray/gamma ray telescopes. Although small-scale variations in the nebula are well-known, since the start of science operations of the Fermi Gamma-ray Burst Monitor (GBM) in August 2008 a 7% (70 mcrab) decline has been observed in the overall Crab Nebula flux in the 15-50 keV band, measured with the Earth occultation technique. This decline is independently confirmed in the 15-50 keV band with three other instruments: the Swift Burst Alert Telescope (Swift/BAT), the Rossi X-ray Timing Explorer Proportional Counter Array (RXTE/PCA), and the INTErnational Gamma-Ray Astrophysics Laboratory Imager on Board INTEGRAL (IBIS). A similar decline is also observed in the 3 - 15 keV data from the RXTE/PCA and in the 50 - 100 keV band with GBM, Swift/BAT, and INTEGRAL/IBIS. The change in the pulsed flux measured with RXTE/PCA since 1999 is consistent with the pulsar spin-down, indicating that the observed changes are nebular. Correlated variations in the Crab Nebula flux on a 3 year timescale are also seen independently with the PCA, BAT, and IBIS from 2005 to 2008, with a flux minimum in April 2007. As of August 2010, the current flux has declined below the 2007 minimum.

  19. Burns and injuries resulting from the use of gel candles.

    Science.gov (United States)

    Pickus, E J; Lionelli, G T; Parmele, J B; Lawrence, W T; Korentager, R A

    2001-01-01

    Scented gel candles are common decorative household items composed of gelled mineral oil, fragrances, and dye. Like traditional wax candles, they have an open flame. Because of defective design, there have been several burns and injuries caused by these products. Here we report our experience with a scald burn from a gel candle and describe 34 additional injuries attributed to gel candles previously unreported in the medical literature.

  20. Chaotic dynamics of a candle oscillator

    Science.gov (United States)

    Lee, Mary Elizabeth; Byrne, Greg; Fenton, Flavio

    The candle oscillator is a simple, fun experiment dating to the late nineteenth century. It consists of a candle with a rod that is transverse to its long axis, around which it is allowed to pivot. When both ends of the candle are lit, an oscillatory motion will initiate due to different mass loss as a function of the flame angle. Stable oscillations can develop due to damping when the system has friction between the rod and the base where the rod rests. However, when friction is minimized, it is possible for chaos to develop. In this talk we will show periodic orbits found in the system as well as calculated, maximal Lyapunov exponents. We show that the system can be described by three ordinary differential equations (one each for angle, angular velocity and mass loss) that can reproduce the experimental data and the transition from stable oscillations to chaotic dynamics as a function of damping.

  1. Christmas-candle Senna:An ornamental and pharmaceutical plant

    Science.gov (United States)

    Christmas candle (Senna alata L.) is an underutilized legume. The USDA, ARS, PGRCU curates only 2 accessions of Christmas candle. Christmas candle plants were transplanted from about 21 day-old seedlings with further transplanting to larger pots containing potting soil as the plants grew larger. Ho...

  2. 75 FR 44224 - Grant of Authority for Subzone Status; Yankee Candle Corporation (Candles and Gift Sets); Whately...

    Science.gov (United States)

    2010-07-28

    ... the Federal Register (75 FR 3705-3706, 1-22-2010) and the application has been processed pursuant to... Foreign-Trade Zones Board Grant of Authority for Subzone Status; Yankee Candle Corporation (Candles and... application to the Board for authority to establish a special-purpose subzone at the candle and gift...

  3. 75 FR 3705 - Foreign-Trade Zone 201-Holyoke, MA; Application for Subzone; Yankee Candle Corporation (Candles...

    Science.gov (United States)

    2010-01-22

    ... Foreign-Trade Zones Board Foreign-Trade Zone 201--Holyoke, MA; Application for Subzone; Yankee Candle Corporation (Candles and Gift Sets); Whately and South Deerfield, MA An application has been submitted to the..., grantee of FTZ 201, requesting special-purpose subzone status for the candle and gift set...

  4. Neutron flux from a 14‐MeV neutron generator with tungsten filter for research in NDA methods for nuclear safeguards and security

    OpenAIRE

    RENNHOFER Harald; PEDERSEN Bent; CROCHEMORE Jean-Michel

    2009-01-01

    The Joint Research Centre has taken into operation a new experimental device designed for research in the fields of nuclear safeguards and security applications. The research projects currently undertaken include detection of shielded contraband materials, detection of fissile materials, and mass determination of small fissile materials in shielded containers. The device, called the Pulsed Neutron Interrogation Test Assembly (PUNITA), incorporates a pulsed 14‐MeV (D‐T) neutron generator and a...

  5. Safeguards -Safeguards system development support-

    International Nuclear Information System (INIS)

    This project mainly focused to technically support national safeguards inspection which is scheduled in the beginning of 1997. It includes non-destructive assay of nuclear fuels, analysis on inspection and environmental samples, remote monitoring of nuclear activities and its analysis, survey on remote sensing of satellite for safeguards application. Non-destructive assay of nuclear fuels dealt with development on verification of spent fuels with emphasis to fabrication of inspection tools with surveillance and gamma measurement on CANDU spent fuels. For sample analysis, study was carried out on process inspection sample analysis method. In addition to this, ultra low background laboratory was set up to execute environmental and swipe samples and sample treatment techniques including water, soil, plant, et al. were researched. Tritiums which were sampled around power plants were analysed. With cooperation of Satellite Technology Research Center of KAIST, use of civilian satellite imagery was surveyed. To train facility operators for safeguards, various technology on non-destructive assay was lectured to personnel of Korea Electric Power Corporation. And to enhance out capabilities, non-destructive assay training was done at Los Alamos National Lab. of U.S. through the agreement of MOST and DOE agreement, and information on DA technology was exchanged at Nuclear Material Control Center of Japan. (author). 22 tabs., 52 figs., 53 refs

  6. Development process of collecting and recycling of wasted graveyard candles

    OpenAIRE

    Košmrlj, Nadja

    2011-01-01

    Slovenia is one of the countries in which we use most graveyard candles. Every year we light 23 million candles and thus create 4.000 tons of waste. Until recently, we have dumped wasted candles in a municipal waste landfill along with other waste. The majority of the candles are made of polyvinyl chloride (PVC), which is dangerous to the environment due to the release of chlorine and organic substances. The Decree of management with wasted graveyard candles entered into force in Slovenia on ...

  7. Type II Cepheids as Extragalactic Distance Candles

    OpenAIRE

    Majaess, Daniel J.; Turner, David G.; Lane, David J.

    2009-01-01

    Extragalactic Type II Cepheids are tentatively identified in photometric surveys of IC 1613, M33, M101, M106, M31, NGC 4603, and the SMC. Preliminary results suggest that Type II Cepheids may play an important role as standard candles, in constraining the effects of metallicity on Cepheid parameters, and in mapping extinction.

  8. Coalescing binaries as possible standard candles

    OpenAIRE

    Capozziello, S.; De Laurentis, M.; Formisano, M.

    2009-01-01

    Gravitational waves detected from well-localized inspiraling binaries would allow to determine, directly and independently, both binary luminosity and redshift. In this case, such systems could behave as "standard candles" providing an excellent probe of cosmic distances up to $z

  9. CANDLE syndrome: a recently described autoinflammatory syndrome.

    Science.gov (United States)

    Tüfekçi, Özlem; Bengoa, ŞebnemYilmaz; Karapinar, Tuba Hilkay; Ataseven, Eda Büke; İrken, Gülersu; Ören, Hale

    2015-05-01

    CANDLE syndrome (chronic atypical neutrophilic dermatosis with lipodystrophy and elevated temperature) is a recently described autoinflammatory syndrome characterized by early onset, recurrent fever, skin lesions, and multisystemic inflammatory manifestations. Most of the patients have been shown to have mutation in PSMB8 gene. Herein, we report a 2-year-old patient with young onset recurrent fever, atypical facies, widespread skin lesions, generalized lymphadenopathy, hepatosplenomegaly, joint contractures, hypertrglyceridemia, lipodystrophy, and autoimmune hemolytic anemia. Clinical features together with the skin biopsy findings were consistent with the CANDLE syndrome. The pathogenesis and treatment of this syndrome have not been fully understood. Increased awareness of this recently described syndrome may lead to recognition of new cases and better understanding of its pathogenesis which in turn may help for development of an effective treatment. PMID:25036278

  10. Stellar candles for the extragalactic distance scale

    CERN Document Server

    Gieren, Wolfgang

    2003-01-01

    This volume reviews the current status with respect to both theory and observation of the extragalactic distance scale. A sufficient accuracy is required both for a precise determination of the cosmological parameters and also in order to achieve a better understanding of physical processes in extragalactic systems. The "standard candles", used to set up the extragalactic distance scale, reviewed in this book include cepheid variables, RR Lyrae variables, novae, Type Ia and Type II supernovae as well as globular clusters and planetary nebulae.

  11. Are Gamma-Ray Bursts Standard Candles?

    OpenAIRE

    Li, Li-Xin

    2007-01-01

    By dividing a sample of 48 long-duration gamma-ray bursts (GRBs) into four groups with redshift from low to high and fitting each group with the Amati relation log Eiso = a + b log Epeak, I find that parameters a and b vary with the mean redshift of the GRBs in each group systematically and significantly. The results suggest that GRBs evolve strongly with the cosmic redshift and hence are not standard candles.

  12. High Redshift Standard Candles: Predicted Cosmological Constraints

    OpenAIRE

    King, A. L.; Davis, T M; Denney, K.; Vestergaard, Marianne; Watson, D

    2013-01-01

    We investigate whether future measurements of high redshift standard candles (HzSCs) will be a powerful probe of dark energy, when compared to other types of planned dark energy measurements. Active galactic nuclei and gamma ray bursts have both been proposed as potential HzSC candidates. Due to their high luminosity, they can be used to probe unexplored regions in the expansion history of the universe. Information from these regions can help constrain the properties of dark energy, and in pa...

  13. Difficulties in Using GRBs as Standard Candles

    Science.gov (United States)

    Goldstein, Adam

    2012-01-01

    Gamma-Ray Bursts have been detected uniformly all over the observable universe, ranging in comoving distance from a few hundred Mpc to a few thousand Mpc, representing the farthest observable objects in the universe. This large distance coverage is highly attractive to those who study cosmology and the history of the early universe since there are no other observed objects that represent such a deep and comprehensive probe of the history of the universe. For this reason, there have been extensive studies into the possibility of using GRBs as standard candles much like Type Ia Supernovae, even though little is known about the physical mechanism that produces the observed burst of gamma-rays. We discuss the attempts at defining GRBs as standard candles, such as the search for a robust luminosity indicator, pseudo-redshift predictions, the complications that emission collimation introduces into the estimation of the rest-frame energetics, and the difficulty introduced by the widely varying observed properties of GRBs. These topics will be examined with supporting data and analyses from both Fermi and Swift observations. Problems with current studies using GRBs as standard candles will be noted as well as potential paths forward to solve these problems.

  14. CANDLE Syndrome: orodfacial manifestations and dental implications.

    Science.gov (United States)

    Roberts, T; Stephen, L; Scott, C; di Pasquale, T; Naser-Eldin, A; Chetty, M; Shaik, S; Lewandowski, L; Beighton, P

    2015-01-01

    A South African girl with CANDLE Syndrome is reported with emphasis on the orodental features and dental management. Clinical manifestations included short stature, wasting of the soft tissue of the arms and legs, erythematous skin eruptions and a prominent abdomen due to hepatosplenomegaly. Generalized microdontia, confirmed by tooth measurement and osteopenia of her jaws, confirmed by digitalized radiography, were previously undescribed syndromic components. Intellectual impairment posed problems during dental intervention. The carious dental lesions and poor oral hygiene were treated conservatively under local anaesthetic. Prophylactic antibiotics were administered an hour before all procedures.Due to the nature of her general condition, invasive dental procedures were minimal. Regular follow-ups were scheduled at six monthly intervals. During this period, her overall oral health status had improved markedly.The CANDLE syndrome is a rare condition with grave complications including immunosuppression and diabetes mellitus. As with many genetic disorders, the dental manifestations are often overshadowed by other more conspicuous and complex syndromic features. Recognition of both the clinical and oral changes that occur in the CANDLE syndrome facilitates accurate diagnosis and appropriate dental management of this potentially lethal condition. PMID:26711936

  15. Electrochemical supercapacitor behaviour of functionalized candle flame carbon soot

    Indian Academy of Sciences (India)

    C Justin Raj; Byung Chul Kim; Bo-Bae Cho; Won-Je Cho; Sung-Jin Kim; Sang Yeup Park; Kook Hyun Yu

    2016-02-01

    The electrochemical supercapacitor behaviour of bare, washed and nitric acid functionalized candle flame carbon soots were reported. Crystallinity and the morphology of the candle soots were recorded using X-ray diffraction analysis, scanning and transmission electron microscopy, respectively. The nitric acid functionalized candle soot showed an improved Brunauer–Emmett–Teller surface area of 137.93 from 87.495 m$^2$ g$^{−1}$ of washed candle soot. The presence of various functional groups in candle soots and the development of oxygen functionalities in the functionalized candle soot were examined through Fourier transform infrared spectroscopy and energy-dispersive X-ray analysis. Raman spectra showed the characteristic peaks corresponding to the D (diamond) and G (graphite) phase of carbon present in the candle soots. The electrochemical characterization was performed by cyclic voltammetry, galvanostatic charge/discharge test and impedance spectroscopy in 1MH2SO4 electrolyte. The functionalized candle soot electrode showed an enhanced specific capacitance value of 187 F g$^{−1}$ at 0.15 A g$^{−1}$ discharge current density, which is much higher than that of bare and washed candle soot electrodes.

  16. CANDLE reactor: an option for simple, safe, high nuclear proliferation resistant , small waste and efficient fuel use reactor

    International Nuclear Information System (INIS)

    The innovative nuclear energy systems have been investigated intensively for long period in COE-INES program and CRINES activities in Tokyo Institute of Technology. Five requirements; sustainability, safety, waste, nuclear-proliferation, and economy; are considered as inevitable requirements for nuclear energy. Characteristics of small LBE cooled CANDLE fast reactor developed in this Institute are discussed for these requirements. It satisfies clearly four requirements; safety, nonproliferation and safeguard, less wastes and sustainability. For the remaining requirement, economy, a high potential to satisfy this requirement is also shown

  17. Neutron flux from a 14-MeV neutron generator with tungsten filter for research in NDA methods for nuclear safeguards and security

    International Nuclear Information System (INIS)

    The Joint Research Centre has taken into operation a new experimental device designed for research in the fields of nuclear safeguards and security applications. The research projects currently undertaken include detection of shielded contraband materials, detection of fissile materials, and mass determination of small fissile materials in shielded containers. The device, called the Pulsed Neutron Interrogation Test Assembly (PUNITA), incorporates a pulsed 14-MeV (D-T) neutron generator and a large graphite mantle surrounding the sample cavity. By pulsing the neutron generator with a frequency in the range of 10 to 150 Hz, a sample may be interrogated first by fast neutrons and a few hundred micro-seconds later by a pure thermal neutron flux. The permanent detection systems incorporated in PUNITA include 3He neutrons detectors, HPGe gamma detectors, and lanthanum bromide scintillation detectors.We have studied the effects of placing a tungsten liner around the neutron generator target. The 14-MeV neutrons induce (n, 2n) and (n, 3n) reactions. In addition the mean neutron energy emitted from generator/tungsten assembly is reduced to about 1 MeV. Both of these effects increase the thermal neutron flux in the sample cavity. The paper describes the observed advantages of the tungsten liner with respect to increase in thermal flux, and better shielding capabilities of the nearby gamma and neutron detectors.

  18. 75 FR 38121 - Petroleum Wax Candles From China

    Science.gov (United States)

    2010-07-01

    ... from China (51 FR 30686). Following first five-year reviews by Commerce and the Commission, effective... candles from China (64 FR 51514). Following second five-year reviews by Commerce and the Commission... petroleum wax candles from China (70 FR 56890, September 29, 2005). The Commission is now conducting a...

  19. Sharing the Arts of the Blue Ridge Mountains. Candles.

    Science.gov (United States)

    Holman, Martha; Gailey, Lamar

    This module on candles is one of eight modules designed to provide instruction on authentic Blue Ridge Mountain crafts to adult basic education students at a low cost. Contents include notes on the history of candle making; process used, including equipment and materials, as well as method described narratively and graphically; and the followup,…

  20. Safeguards Implementation at KAERI

    International Nuclear Information System (INIS)

    The main objective of the safeguards implementation activities is to assure that there are no diversions of declared nuclear material and/or no undeclared activity. The purpose of safeguards implementation activities is the assistance facility operators to meet the safeguards criteria set forth by the Atomic Energy Safety Acts and Regulations. In addition, the nuclear material and technology control team has acted as a contact point for domestic and international safeguards inspection activities and for the relevant safeguards cooperation. Domestic inspections were successfully carried out at the KAERI nuclear facilities pursuant to the domestic laws and regulations in parallel with the IAEA safeguards inspections. It is expected that safeguards work will be increased due to the pyro-related facilities such as PRIDE, ACPF and DUPIC, for which the IAEA is making an effort to establish safeguards approach. KAERI will actively cope with the plan of the NSSC by changing its domestic inspection regulations on the accounting and control of nuclear materials

  1. Safeguards Implementation at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Juang; Lee, Sung Ho; Lee, Byung-Doo; Kim, Hyun-Sook [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    The main objective of the safeguards implementation activities is to assure that there are no diversions of declared nuclear material and/or no undeclared activity. The purpose of safeguards implementation activities is the assistance facility operators to meet the safeguards criteria set forth by the Atomic Energy Safety Acts and Regulations. In addition, the nuclear material and technology control team has acted as a contact point for domestic and international safeguards inspection activities and for the relevant safeguards cooperation. Domestic inspections were successfully carried out at the KAERI nuclear facilities pursuant to the domestic laws and regulations in parallel with the IAEA safeguards inspections. It is expected that safeguards work will be increased due to the pyro-related facilities such as PRIDE, ACPF and DUPIC, for which the IAEA is making an effort to establish safeguards approach. KAERI will actively cope with the plan of the NSSC by changing its domestic inspection regulations on the accounting and control of nuclear materials.

  2. Nuclear safeguards technology handbook

    Energy Technology Data Exchange (ETDEWEB)

    1977-12-01

    The purpose of this handbook is to present to United States industrial organizations the Department of Energy's (DOE) Safeguards Technology Program. The roles and missions for safeguards in the U.S. government and application of the DOE technology program to industry safeguards planning are discussed. A guide to sources and products is included. (LK)

  3. Nuclear safeguards technology handbook

    International Nuclear Information System (INIS)

    The purpose of this handbook is to present to United States industrial organizations the Department of Energy's (DOE) Safeguards Technology Program. The roles and missions for safeguards in the U.S. government and application of the DOE technology program to industry safeguards planning are discussed. A guide to sources and products is included

  4. Numerical Analysis of Flow Field in Ceramic Filter During Pulse Cleaning

    Institute of Scientific and Technical Information of China (English)

    姬忠礼; 彭书; 谭立村

    2003-01-01

    In the commercial utilization of rigid ceramic filters, the performance of pulse cleaning has crucial effects on the long-term stable operation. In order to get a clear insight into the nature of this cleaning process and provide a solid basis for industrial applications, the flow in ceramic candle filter was investigated. The flow in the pulse-jetspace and inside the ceramic candle is regarded as two- dimensional, unsteady, compressible flow, and numerical simulation is carried out by computational fluid dynamics. The numerical predictions of flow field are in good agreement with the experimental measurements. Effects of the candle diameter, the separation distance between the nozzle and the candle injector and the length of the candle on the flowfield have been numerically analyzed to provide the basis for the optimum design of the pulse cleaning system.

  5. Nuclear safeguards; Salvaguardias nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Zurron, O.

    2015-07-01

    Safeguards control at the Juzbado Plant is implemented through the joint IAEA/EURATOM partnership approach in force within the European Union for all nuclear facilities. this verification agreement is designed to minimize burden on the operators whilst ensuring that both inspectorate achieve the objectives related to their respective safeguards regimes. This paper outlines the safeguards approaches followed by the inspectorate and the particularities of the Juzbado Plants nuclear material accountancy and control system. (Authors)

  6. Safeguards resource management

    International Nuclear Information System (INIS)

    Protecting nuclear materials is a challenging problem for facility managers. To counter the broad spectrum of potential threats, facility managers rely on diverse safeguards measures, including elements of physical protection, material control and accountability, and human reliability programs. Deciding how to upgrade safeguards systems involves difficult tradeoffs between increased protection and the costs and operational impact of protection measures. Effective allocation of safeguards and security resources requires a prioritization of system upgrades based on a relative measure of upgrade benefits to upgrade costs. Analytical tools are needed to help safeguards managers measure the relative benefits and costs and allocate their limited resources to achieve balanced, cost-effective protection against the full spectrum of threats. This paper presents a conceptual approach and quantitative model that have been developed by Lawrence Livermore National Laboratory to aid safeguards managers. The model is in the preliminary stages of implementation, and an effort is ongoing to make the approach and quantitative model available for general use. The model, which is designed to complement existing nuclear safeguards evaluation tools, incorporates a variety of factors and integrates information on the likelihood of potential threats, safeguards capabilities to defeat threats, and the relative consequences if safeguards fail. The model uses this information to provide an overall measure for comparing safeguards upgrade projects at a facility

  7. Violence: Safeguarding Our Children.

    Science.gov (United States)

    Our Children, 1995

    1995-01-01

    This adaptation of the National Parent Teacher Association (PTA) booklet "Safeguarding Your Children" discusses cooperative efforts of communities, schools, and homes to protect children from violence. (SM)

  8. The Canadian safeguards program

    International Nuclear Information System (INIS)

    In support of the Treaty on the Non-Proliferation of Nuclear Weapons Canada provides technical support to the International Atomic Energy Agency for the development of safeguards relevant to Canadian designed and built nuclear facilities. Some details of this program are discussed, including the philosophy and development of CANDU safeguards systems; the unique equipment developed for these systems; the provision of technical experts; training programs; liaison with other technical organizations; research and development; implementation of safeguards systems at various nuclear facilities; and the anticipated future direction of the safeguards program

  9. Comparison of cosmological models using standard rulers and candles

    OpenAIRE

    Li, Xiaolei; Cao, Shuo; Zheng, Xiaogang; Li, Song; Biesiada, Marek

    2015-01-01

    In this paper, we used standard rulers and standard candles (separately and jointly) to explore five popular dark energy models under assumption of spatial flatness of the Universe. As standard rulers, we used a data set comprising 118 galactic-scale strong lensing systems (individual standard rulers if properly calibrated for the mass density profile) combined with BAO diagnostics (statistical standard ruler). Supernovae Ia served asstandard candles. Unlike in the most of previous statistica...

  10. Strenghening Safeguards Authorities and Institutions

    Energy Technology Data Exchange (ETDEWEB)

    Goodman,M.; Lockwood, d.; Rosenthal, M.D.; Tape, J.W.

    2008-06-06

    The International Atomic Energy Agency (IAEA) safeguards system has changed in major ways from the establishment of the IAEA in 1957 until the present. Changes include strengthening the legal framework of safeguards; improvements in concepts and approaches for safeguards implementation; and significant improvements in the technical tools available to inspectors. In this paper, we explore three broad areas related to strengthening safeguards authorities and institutions: integrated safeguards and State-Level Approaches; special inspections; and NPT withdrawal and the continuation of safeguards.

  11. The safeguards options study

    International Nuclear Information System (INIS)

    The Safeguards Options Study was initiated to aid the International Safeguards Division (ISD) of the DOE Office of Arms Control and Nonproliferation in developing its programs in enhanced international safeguards. The goal was to provide a technical basis for the ISD program in this area. The Safeguards Options Study has been a cooperative effort among ten organizations. These are Argonne National Laboratory, Brookhaven National Laboratory, Idaho National Engineering Laboratory, Lawrence Livermore National Laboratory, Los Alamos National Laboratory, Mound Laboratory, Oak Ridge National Laboratory, Pacific Northwest Laboratories, Sandia National Laboratories, and Special Technologies Laboratory. Much of the Motivation for the Safeguards Options Study is the recognition after the Iraq experience that there are deficiencies in the present approach to international safeguards. While under International Atomic Energy Agency (IAEA) safeguards at their declared facilities, Iraq was able to develop a significant weapons program without being noticed. This is because negotiated safeguards only applied at declared sites. Even so, their nuclear weapons program clearly conflicted with Iraq's obligations under the Nuclear Nonproliferation Treaty (NPT) as a nonnuclear weapon state

  12. The safeguards options study

    Energy Technology Data Exchange (ETDEWEB)

    Hakkila, E.A.; Mullen, M.F.; Olinger, C.T.; Stanbro, W.D. [Los Alamos National Lab., NM (United States); Olsen, A.P.; Roche, C.T.; Rudolph, R.R. [Argonne National Lab., IL (United States); Bieber, A.M.; Lemley, J. [Brookhaven National Lab., Upton, NY (United States); Filby, E. [Idaho National Engineering Lab., Idaho Falls, ID (United States)] [and others

    1995-04-01

    The Safeguards Options Study was initiated to aid the International Safeguards Division (ISD) of the DOE Office of Arms Control and Nonproliferation in developing its programs in enhanced international safeguards. The goal was to provide a technical basis for the ISD program in this area. The Safeguards Options Study has been a cooperative effort among ten organizations. These are Argonne National Laboratory, Brookhaven National Laboratory, Idaho National Engineering Laboratory, Lawrence Livermore National Laboratory, Los Alamos National Laboratory, Mound Laboratory, Oak Ridge National Laboratory, Pacific Northwest Laboratories, Sandia National Laboratories, and Special Technologies Laboratory. Much of the Motivation for the Safeguards Options Study is the recognition after the Iraq experience that there are deficiencies in the present approach to international safeguards. While under International Atomic Energy Agency (IAEA) safeguards at their declared facilities, Iraq was able to develop a significant weapons program without being noticed. This is because negotiated safeguards only applied at declared sites. Even so, their nuclear weapons program clearly conflicted with Iraq`s obligations under the Nuclear Nonproliferation Treaty (NPT) as a nonnuclear weapon state.

  13. ADVANCED HOT GAS FILTER DEVELOPMENT

    Energy Technology Data Exchange (ETDEWEB)

    E.S. Connolly; G.D. Forsythe

    2000-09-30

    DuPont Lanxide Composites, Inc. undertook a sixty-month program, under DOE Contract DEAC21-94MC31214, in order to develop hot gas candle filters from a patented material technology know as PRD-66. The goal of this program was to extend the development of this material as a filter element and fully assess the capability of this technology to meet the needs of Pressurized Fluidized Bed Combustion (PFBC) and Integrated Gasification Combined Cycle (IGCC) power generation systems at commercial scale. The principal objective of Task 3 was to build on the initial PRD-66 filter development, optimize its structure, and evaluate basic material properties relevant to the hot gas filter application. Initially, this consisted of an evaluation of an advanced filament-wound core structure that had been designed to produce an effective bulk filter underneath the barrier filter formed by the outer membrane. The basic material properties to be evaluated (as established by the DOE/METC materials working group) would include mechanical, thermal, and fracture toughness parameters for both new and used material, for the purpose of building a material database consistent with what is being done for the alternative candle filter systems. Task 3 was later expanded to include analysis of PRD-66 candle filters, which had been exposed to actual PFBC conditions, development of an improved membrane, and installation of equipment necessary for the processing of a modified composition. Task 4 would address essential technical issues involving the scale-up of PRD-66 candle filter manufacturing from prototype production to commercial scale manufacturing. The focus would be on capacity (as it affects the ability to deliver commercial order quantities), process specification (as it affects yields, quality, and costs), and manufacturing systems (e.g. QA/QC, materials handling, parts flow, and cost data acquisition). Any filters fabricated during this task would be used for product qualification tests

  14. Brightest cluster galaxies as standard candles

    Science.gov (United States)

    Postman, Marc; Lauer, Tod R.

    1995-01-01

    We investigate the use of brightest cluster galaxies (BCGs) as standard candles for measuring galaxy peculiar velocities on large scales. We have obtained precise large-format CCD surface photometry and redshifts for an all-sky, volume-limited (z less than or = 0.05) sample of 199 BCG. We reinvestigate the Hoessel (1980) relationship between the metric luminosity, L(sub m), within the central 10 kpc/h of the BCGs and the logarithmic slope of the surface brightness profile, alpha. The L(sub m)-alpha relationship reduces the cosmic scatter in L(sub m) from 0.327 mag to 0.244 mag, yielding a typical distance accuracy of 17% per BCG. Residuals about the L(sub m)-alpha relationship are independent of BCG luminosity, BCG B - R(sub c) color, BCG location within the host cluster, and richness of the host cluster. The metric luminosity is independent of cluster richness even before correcting for its dependence on alpha, which provides further evidence for the unique nature of the BCG luminosity function. Indeed, the BCG luminosity function, both before and after application of the alpha-correction, is consistent with a single Gaussian distribution. Half the BCGs in the sample show some evidence of small color gradients as a function of radius within their central 50 kpc/h regions but with almost equal numbers becoming redder as becoming bluer. However, with the central 10 kpc/h the colors are remarkably constant -- the mean B - R(sub c) color is 1.51 with a dispersion of only 0.06 mag. The narrow photometric and color distributions of the BCGs, the lack of 'second-parameter' effects, as well as the unique rich cluster environment of BCGs, argue that BCGs are the most homogeneous distance indicators presently available for large-scale structure research.

  15. Intrinsic scatter of the luminosity relation, redshift distribution of the standard candles, and the constraining capability

    OpenAIRE

    Qi, Shi

    2015-01-01

    Standard candles are one of the most important tools to study the universe. In this paper, the constraints of standards candles on the cosmological parameters are estimated for different cases. The dependence of the constraints on the intrinsic scatter of the luminosity relation and the redshift distribution of the standard candles is specifically investigated. The results, especially for the constraints on the components of the universe, clearly show that constraints from standard candles at...

  16. Part 7. Safeguards

    International Nuclear Information System (INIS)

    This report describes fissile nuclear material safeguards technology, both current and developmental, and discusses the possible application of this technology to FBR systems. The proliferation risks associated with both subnational and national-level diversion are addressed

  17. Strengthening regional safeguards

    International Nuclear Information System (INIS)

    Nuclear cooperation between Argentina and Brazil has been growing since the early 1980's and as it grew, so did cooperation with the US Department of Energy (DOE). The Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC) was formed in December 1991 to operate the Common System of Accounting and Control of Nuclear Materials (SCCC). In April 1994, ABACC and the DOE signed an Agreement of Cooperation in nuclear material safeguards. This cooperation has included training safeguards inspectors, exchanging nuclear material measurement and containment and surveillance technology, characterizing reference materials, and studying enrichment plant safeguards. The goal of the collaboration is to exchange technology, evaluate new technology in Latin American nuclear facilities, and strengthen regional safeguards. This paper describes the history of the cooperation, its recent activities, and future projects. The cooperation is strongly supported by all three governments: the Republics of Argentina and Brazil and the United States

  18. Strengthening regional safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Palhares, L.; Almeida, G.; Mafra, O. [Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials, Rio de Janeiro (Brazil)] [and others

    1996-08-01

    Nuclear cooperation between Argentina and Brazil has been growing since the early 1980`s and as it grew, so did cooperation with the US Department of Energy (DOE). The Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC) was formed in December 1991 to operate the Common System of Accounting and Control of Nuclear Materials (SCCC). In April 1994, ABACC and the DOE signed an Agreement of Cooperation in nuclear material safeguards. This cooperation has included training safeguards inspectors, exchanging nuclear material measurement and containment and surveillance technology, characterizing reference materials, and studying enrichment plant safeguards. The goal of the collaboration is to exchange technology, evaluate new technology in Latin American nuclear facilities, and strengthen regional safeguards. This paper describes the history of the cooperation, its recent activities, and future projects. The cooperation is strongly supported by all three governments: the Republics of Argentina and Brazil and the United States.

  19. Optimized Design and Discussion on Middle and Large CANDLE Reactors

    Directory of Open Access Journals (Sweden)

    Xiaoming Chai

    2012-08-01

    Full Text Available CANDLE (Constant Axial shape of Neutron flux, nuclide number densities and power shape During Life of Energy producing reactor reactors have been intensively researched in the last decades [1–6]. Research shows that this kind of reactor is highly economical, safe and efficiently saves resources, thus extending large scale fission nuclear energy utilization for thousands of years, benefitting the whole of society. For many developing countries with a large population and high energy demands, such as China and India, middle (1000 MWth and large (2000 MWth CANDLE fast reactors are obviously more suitable than small reactors [2]. In this paper, the middle and large CANDLE reactors are investigated with U-Pu and combined ThU-UPu fuel cycles, aiming to utilize the abundant thorium resources and optimize the radial power distribution. To achieve these design purposes, the present designs were utilized, simply dividing the core into two fuel regions in the radial direction. The less active fuel, such as thorium or natural uranium, was loaded in the inner core region and the fuel with low-level enrichment, e.g. 2.0% enriched uranium, was loaded in the outer core region. By this simple core configuration and fuel setting, rather than using a complicated method, we can obtain the desired middle and large CANDLE fast cores with reasonable core geometry and thermal hydraulic parameters that perform safely and economically; as is to be expected from CANDLE. To assist in understanding the CANDLE reactor’s attributes, analysis and discussion of the calculation results achieved are provided.

  20. Overcoming Safeguards Challenges

    International Nuclear Information System (INIS)

    The focus of the 2010 IAEA International Safeguards Symposium was how best, from a technical perspective, to prepare for future verification challenges during this time of change. By bringing together the leading experts in the field from across the world, this symposium provided an opportunity for stakeholders to explore possible solutions in support of the IAEA's nuclear verification mission, and to identify areas where the different stakeholders in the safeguards business can help address these challenges

  1. International safeguards data authentication

    International Nuclear Information System (INIS)

    The International Safeguards community is becoming increasingly reliant on information stored in electronic form. In international monitoring and related activities it must be possible to verify and maintain the integrity of this electronic information. This paper discusses the use of data authentication technology to assist in accomplishing this task. The paper provides background information, identifies the relevance to international safeguards, discusses issues related to export controls, algorithm patents, key management and the use of commercial vs. custom software

  2. International safeguards data authentication

    Energy Technology Data Exchange (ETDEWEB)

    Melton, R.B.; Smith, C.E.; DeLand, S.M.; Manatt, D.R.

    1996-07-01

    The International Safeguards community is becoming increasingly reliant on information stored in electronic form. In international monitoring and related activities it must be possible to verify and maintain the integrity of this electronic information. This paper discusses the use of data authentication technology to assist in accomplishing this task. The paper provides background information, identifies the relevance to international safeguards, discusses issues related to export controls, algorithm patents, key management and the use of commercial vs. custom software.

  3. Safeguards and physics measurements

    Energy Technology Data Exchange (ETDEWEB)

    Carchon, R

    2002-04-01

    SCK-CEN's programme on safeguards and physics measurements involves gamma and neutron dosimetry, calibrations and irradiations, electronic support, metrology of various samples including internal contamination of human beings, of waste barrels and of fissile materials, neutron activation analysis, and radioisotope source preparation. The document reports on the main activities and achievements of the sections 'Instrumentation, Calibration and Dosimetry' and 'Safeguards and Nuclear Physics Measurements'.

  4. Measuring Safeguards Culture

    Energy Technology Data Exchange (ETDEWEB)

    Frazar, Sarah L.; Mladineo, Stephen V.

    2011-07-19

    As the International Atomic Energy Agency (IAEA) implements a State Level Approach to its safeguards verification responsibilities, a number of countries are beginning new nuclear power programs and building new nuclear fuel cycle faculties. The State Level approach is holistic and investigatory in nature, creating a need for transparent, non-discriminatory judgments about a state's nonproliferation posture. In support of this need, the authors previously explored the value of defining and measuring a state's safeguards culture. We argued that a clear definition of safeguards culture and an accompanying set of metrics could be applied to provide an objective evaluation and demonstration of a country's nonproliferation posture. As part of this research, we outlined four high-level metrics that could be used to evaluate a state's nuclear posture. We identified general data points. This paper elaborates on those metrics, further refining the data points to generate a measurable scale of safeguards cultures. We believe that this work could advance the IAEA's goals of implementing a safeguards system that is fully information driven, while strengthening confidence in its safeguards conclusions.

  5. Safeguards Culture: lesson learned

    International Nuclear Information System (INIS)

    After the discovery of Iraq's clandestine nuclear program in 1991, the international community developed new tools for evaluating and demonstrating states' nuclear intentions. The International Atomic Energy Agency (IAEA) developed a more holistic approach toward international safeguards verification to garner more complete information about states' nuclear activities. This approach manifested itself in State Level Evaluations, using information from a variety of sources, including the implementation of integrated safeguards in Member States, to reach a broader conclusion. Those wishing to exhibit strong nonproliferation postures to a more critical international community took steps to demonstrate their nonproliferation 'bona fides'. As these Member States signed and brought into force the Additional Protocol, submitted United Nations Security Council Resolution 1540 reports and strengthened their export control laws, the international community began to consider the emergence of so-called safeguards cultures. Today, safeguards culture can be a useful tool for measuring nonproliferation postures, but so far its impact on the international safeguards regime has been under appreciated. There is no agreed upon definition for safeguards culture nor agreement on how it should be measured.

  6. Proper Use of Candles During a Power Outage

    Centers for Disease Control (CDC) Podcasts

    2006-08-10

    Home fires are a threat after a natural disaster and fire trucks may have trouble getting to your home. If the power is out, use flashlights or other battery-powered lights if possible, instead of candles.  Created: 8/10/2006 by Emergency Communications System.   Date Released: 8/20/2008.

  7. Using Quasars as Standard Candles for Studying Dark Energy

    DEFF Research Database (Denmark)

    Denney, Kelly D.; Vestergaard, Marianne; Watson, D.;

    2012-01-01

    We have recently demonstrated (Watson et al. 2011, ApJ, 740, L49) that quasars, or more generally active galactic nuclei (AGNs), can be used as standard candles for measuring distances in the universe, similar to Type Ia supernovae (SNe). Here, we present the initial findings of this new method...

  8. 75 FR 80843 - Petroleum Wax Candles From China

    Science.gov (United States)

    2010-12-23

    ....2(f)). Background The Commission instituted this review on July 1, 2010 (75 FR 38121) and determined on October 4, 2010 that it would conduct an expedited review (75 FR 63200, October 14, 2010). The... COMMISSION Petroleum Wax Candles From China Determination On the basis of the record \\1\\ developed in...

  9. Demonstrating Sound Wave Propagation with Candle Flame and Loudspeaker

    Science.gov (United States)

    Hrepic, Zdeslav; Nettles, Corey; Bonilla, Chelsea

    2013-01-01

    The motion of a candle flame in front of a loudspeaker has been suggested as a productive demonstration of the longitudinal wave nature of sound. The demonstration has been used also as a research tool to investigate students' understanding about sound. The underpinning of both applications is the expectation of a horizontal, back-and-forth…

  10. Gamma-ray burst supernovae as standardizable candles

    Energy Technology Data Exchange (ETDEWEB)

    Cano, Z., E-mail: zewcano@gmail.com [Centre for Astrophysics and Cosmology, Science Institute, University of Iceland, Reykjavik (Iceland)

    2014-10-20

    A long-duration gamma-ray burst (GRB) marks the violent end of a massive star. GRBs are rare in the universe, and their progenitor stars are thought to possess unique physical properties such as low metal content and rapid rotation, while the supernovae (SNe) that are associated with GRBs are expected to be highly aspherical. To date, it has been unclear whether GRB-SNe could be used as standardizable candles, with contrasting conclusions found by different teams. In this paper, I present evidence that GRB-SNe have the potential to be used as standardizable candles and show that a statistically significant relation exists between the brightness and width of their decomposed light curves relative to a template SN. Every single nearby spectroscopically identified GRB-SN for which the rest frame and host contributions have been accurately determined follows this relation. Additionally, it is shown that not only GRB-SNe, but perhaps all SNe whose explosions are powered by a central engine may eventually be used as a standardizable candle. Finally, I suggest that the use of GRB-SNe as standardizable candles likely arises from a combination of the viewing angle and similar explosion geometry in each event, the latter of which is influenced by the explosion mechanism of GRB-SNe.

  11. I Wish We Could Be Together: The Candle Ceremony.

    Science.gov (United States)

    Owens, Caroline V.

    1999-01-01

    Notes that young children need to express joys and sadness; discusses candle ceremony designed for discussions of grief. Suggests teachers inform parents of the ceremony and solicit their help in preparing children, resolve not to try to solve all problems that may be discussed, inform children the moments are private, and plan for difficult…

  12. Safeguards by Design Challenge

    Energy Technology Data Exchange (ETDEWEB)

    Alwin, Jennifer Louise [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-09-13

    The International Atomic Energy Agency (IAEA) defines Safeguards as a system of inspection and verification of the peaceful uses of nuclear materials as part of the Nuclear Nonproliferation Treaty. IAEA oversees safeguards worldwide. Safeguards by Design (SBD) involves incorporation of safeguards technologies, techniques, and instrumentation during the design phase of a facility, rather that after the fact. Design challenge goals are the following: Design a system of safeguards technologies, techniques, and instrumentation for inspection and verification of the peaceful uses of nuclear materials. Cost should be minimized to work with the IAEA’s limited budget. Dose to workers should always be as low are reasonably achievable (ALARA). Time is of the essence in operating facilities and flow of material should not be interrupted significantly. Proprietary process information in facilities may need to be protected, thus the amount of information obtained by inspectors should be the minimum required to achieve the measurement goal. Then three different design challenges are detailed: Plutonium Waste Item Measurement System, Marine-based Modular Reactor, and Floating Nuclear Power Plant (FNPP).

  13. Reporting of safeguards events

    International Nuclear Information System (INIS)

    On June 9, 1987, the Commission published in the Federal Register a final rule revising the reporting requirements for safeguards events. Safeguards events include actual or attempted theft of special nuclear material (SNM); actual or attempted acts or events which interrupt normal operations at power reactors due to unauthorized use of or tampering with machinery, components, or controls; certain threats made against facilities possessing SNM; and safeguards system failures impacting the effectiveness of the system. The revised rule was effective October 8, 1987. On September 14, 1987, the NRC held a workshop in Bethesda, MD, to answer affected licensees' questions on the final rule. This report documents questions discussed at the September 14 meeting, reflects a completed staff review of the answers, and supersedes previous oral comment on the topics covered

  14. Building safeguards infrastructure

    International Nuclear Information System (INIS)

    Much has been written in recent years about the nuclear renaissance - the rebirth of nuclear power as a clean and safe source of electricity around the world. Those who question the nuclear renaissance often cite the risk of proliferation, accidents or an attack on a facility as concerns, all of which merit serious consideration. The integration of three areas - sometimes referred to as 3S, for safety, security and safeguards - is essential to supporting the clean and safe growth of nuclear power, and the infrastructure that supports these three areas should be robust. The focus of this paper will be on the development of the infrastructure necessary to support safeguards, and the integration of safeguards infrastructure with other elements critical to ensuring nuclear energy security

  15. The evolution of IAEA safeguards

    International Nuclear Information System (INIS)

    This, second in a new series of booklets dealing with IAEA safeguards is intended for persons professionally interested in the subject as government officials responsible for non-proliferation or management of nuclear facilities, and practitioners of safeguards - the international and national officials charged with implementing IAEA safeguards. It is also aimed at the broader public concerned with the spread of nuclear weapons and interested in nuclear arms control and disarmament. It presents the situation as IAEA safeguards make 'quantum jump' into new phase characterized by the IAEA as the 'Strengthened Safeguards System'. It includes the historical overview of the International safeguards from 1945-1998; the aims and limitations of IAEA Safeguards; a chapter on how safeguards work in practice; as well as new challenges and opportunities

  16. Nuclear safeguards technology 1986

    International Nuclear Information System (INIS)

    This publication presents the results of the sixth in a series of international symposia on nuclear material safeguards. Development efforts related to safeguards for reprocessing plants constituted over twenty per cent of the programme. Other papers present results of over four years of field testing of near real time material accountancy at a plant in Japan and results for a lesser period of time at a plant in Scotland. Papers reporting work on destructive and non-destructive measurement procedures or equipment constituted another thirty per cent of the programme, more if measurements in reprocessing and poster presentations are included. In honour of the tenth anniversary of the founding of the Safeguards Analytical Laboratory, two sessions were devoted to a review of destructive analytical measurement procedures. Some subjects received only minor attention during the Symposium. The statistical theory of random sampling, safeguards for uranium enrichment plants, material accountancy systems and several other topics appear only incidentally in the programme, but primarily because there are few remaining problems, not because there is little remaining interest

  17. Safeguards system analysis, (1)

    International Nuclear Information System (INIS)

    A system analysis on the implementing safeguards system based on the traditional materials accountancy was done. This report describes about verification methods applied to operator's measurement data, MUF evaluation method, theories on the decision of PIT frequency and designing of inspection plan. (author)

  18. Safeguards techniques and equipment

    International Nuclear Information System (INIS)

    The current booklet is intended to give a full and balanced description of the techniques and equipment used for both nuclear material accountancy and containment and surveillance measures, and for the new safeguards measure of environmental sampling. As new verification measures continue to be developed, the material in the booklet will be periodically reviewed and updated versions issued. (author)

  19. Facility Safeguardability Analysis In Support of Safeguards-by-Design

    Energy Technology Data Exchange (ETDEWEB)

    Philip Casey Durst; Roald Wigeland; Robert Bari; Trond Bjornard; John Hockert; Michael Zentner

    2010-07-01

    The following report proposes the use of Facility Safeguardability Analysis (FSA) to: i) compare and evaluate nuclear safeguards measures, ii) optimize the prospective facility safeguards approach, iii) objectively and analytically evaluate nuclear facility safeguardability, and iv) evaluate and optimize barriers within the facility and process design to minimize the risk of diversion and theft of nuclear material. As proposed by the authors, Facility Safeguardability Analysis would be used by the Facility Designer and/or Project Design Team during the design and construction of the nuclear facility to evaluate and optimize the facility safeguards approach and design of the safeguards system. Through a process of “Safeguards-by-Design” (SBD), this would be done at the earliest stages of project conceptual design and would involve domestic and international nuclear regulators and authorities, including the International Atomic Energy Agency (IAEA). The benefits of the Safeguards-by-Design approach is that it would clarify at a very early stage the international and domestic safeguards requirements for the Construction Project Team, and the best design and operating practices for meeting these requirements. It would also minimize the risk to the construction project, in terms of cost overruns or delays, which might otherwise occur if the nuclear safeguards measures are not incorporated into the facility design at an early stage. Incorporating nuclear safeguards measures is straight forward for nuclear facilities of existing design, but becomes more challenging with new designs and more complex nuclear facilities. For this reason, the facility designer and Project Design Team require an analytical tool for comparing safeguards measures, options, and approaches, and for evaluating the “safeguardability” of the facility. The report explains how preliminary diversion path analysis and the Proliferation Resistance and Physical Protection (PRPP) evaluation

  20. EVOLUTION OF CREATION BUDDHIST LENT CANDLE OF WORK AWARDED IN UBON RATCHATHANI’S LENT CANDLE CONTESTS 2003-2007

    Directory of Open Access Journals (Sweden)

    Sakchai Uttitho

    2012-01-01

    Full Text Available The tradition of Lent candle procession at the Buddhist Lent festival is the grand festival at the national level in Ubon Ratchathani province. From the merit-making tradition concerning Buddhism binding to the way of life of Isan people for the long time, this festival has developed to be a tourist festival at the national level. Later, there have been contests of candle making in continuity. Throughout the past time the contests have promoted creation of candle with different styles contests and stories which are valuable for studying and dissemination in the future. The purposes of this research were to examine the background of the Buddhist Lent candle trees, elements of contests and evaluation of candle trees awarded on Lent candle contests in Ubon Ratchathani province from 2003-2007. The research area covered Ubon Ratchathani provinces where Buddhist Lent candle were created for contests which were the most famous in Thailand. The research procedure used the qualitative research methodology. Data were collected from related literature and field studies using survey, observations, interviews and focus group discussion from a group of totally 35 informants. The findings were presented by means of a descriptive analysis. The results reviewed that candle trees had been made for neatness contests since 1927. In 1977 the tradition of Lent candle procession week was held to be a grand annual festival of the province. Candle trees were contested in 3 types. Later two elements of contest consisted of large-sized candle tree and small-sized candle tree. Concepts of candle tree creation were from the criteria determined by Ubon Ratchathani province. The criteria were different from year to year. The stories to created as candle trees were about Buddhism local culture and identities of Ubon Ratchathani. The same criteria were use for decision making in every type by considering from candle tree base and all elements, The evaluation of candle trees

  1. Comparison of cosmological models using standard rulers and candles

    CERN Document Server

    Li, Xiaolei; Zheng, Xiaogang; Biesiada, Marek; Zhu, Zong-Hong

    2015-01-01

    In this paper, we used standard rulers and standard candles (separately and jointly) to explore five popular dark energy models under assumption of spatial flatness of the Universe. As standard rulers, we used a data set comprising 118 galactic-scale strong lensing systems (individual standard rulers if properly calibrated for the mass density profile) combined with BAO diagnostics (statistical standard ruler). Supernovae Ia served asstandard candles. Unlike in the most of previous statistical studies involving strong lensing systems, we relaxed the assumption of singular isothermal sphere (SIS) in favor of its generalization: the power-law mass density profile. Therefore, along with cosmological model parameters we fitted the power law index and its first derivative with respect to the redshift (thus allowing for mass density profile evolution). It turned out that the best fitted $\\gamma$ parameters are in agreement with each other irrespective of the cosmological model considered. This demonstrates that gal...

  2. Long Gamma-Ray Bursts as standard candles

    CERN Document Server

    Lazzati, D; Ghisellini, G; Nava, L; Firmani, C; Morsony, B; Begelman, M C; Morsony, Brian

    2006-01-01

    As soon as it was realized that long GRBs lie at cosmological distances, attempts have been made to use them as cosmological probes. Besides their use as lighthouses, a task that presents mainly the technological challenge of a rapid deep high resolution follow-up, researchers attempted to find the Holy Grail: a way to create a standard candle from GRB observables. We discuss here the attempts and the discovery of the Ghirlanda correlation, to date the best method to standardize the GRB candle. Together with discussing the promises of this method, we will underline the open issues, the required calibrations and how to understand them and keep them under control. Even though GRB cosmology is a field in its infancy, ongoing work and studies will clarify soon if and how GRBs will be able to keep up to the promises.

  3. Comparison of cosmological models using standard rulers and candles

    Science.gov (United States)

    Li, Xiao-Lei; Cao, Shuo; Zheng, Xiao-Gang; Li, Song; Biesiada, Marek

    2016-05-01

    In this paper, we used standard rulers and standard candles (separately and jointly) to explore five popular dark energy models under the assumption of the spatial flatness of the Universe. As standard rulers, we used a data set comprised of 118 galactic scale strong lensing systems (individual standard rulers if properly calibrated for the mass density profile) combined with BAO diagnostics (statistical standard ruler). Type Ia supernovae served as standard candles. Unlike most previous statistical studies involving strong lensing systems, we relaxed the assumption of a singular isothermal sphere (SIS) in favor of its generalization: the power-law mass density profile. Therefore, along with cosmological model parameters, we fitted the power law index and its first derivative with respect to the redshift (thus allowing for mass density profile evolution). It turned out that the best fitted γ parameters are in agreement with each other, irrespective of the cosmological model considered. This demonstrates that galactic strong lensing systems may provide a complementary probe to test the properties of dark energy. The fits for cosmological model parameters which we obtained are in agreement with alternative studies performed by other researchers. Because standard rulers and standard candles have different parameter degeneracies, a combination of standard rulers and standard candles gives much more restrictive results for cosmological parameters. Finally, we attempted an analysis based on model selection using information theoretic criteria (AIC and BIC). Our results support the claim that the cosmological constant model is still best and there is no (at least statistical) reason to prefer any other more complex model.

  4. Clusters of Galaxies as Standard Candles for Global Observational Cosmology

    OpenAIRE

    Roukema, B. F.

    2001-01-01

    As the largest gravitationally collapsed objects, and as objects with a relatively low space density, clusters of galaxies offer one of the best sets of standard candles for trying to measure basic cosmological parameters such as the injectivity diameter 2r_{inj} (the shortest distance between two topologically lensed images of any object, e.g. cluster) and the out-diameter 2r_{+} (the maximum `size' of the Universe). Present constraints indicate that either of these may be smaller or larger ...

  5. Light a CANDLE. An innovative burnup strategy of nuclear reactors

    International Nuclear Information System (INIS)

    CANDLE is a new burnup strategy for nuclear reactors, which stands for Constant Axial Shape of Neutron Flux, Nuclide Densities and Power Shape During Life of Energy Production. When this candle-like burnup strategy is adopted, although the fuel is fixed in a reactor core, the burning region moves, at a speed proportionate to the power output, along the direction of the core axis without changing the spatial distribution of the number density of the nuclides, neutron flux, and power density. Excess reactivity is not necessary for burnup and the shape of the power distribution and core characteristics do not change with the progress of burnup. It is not necessary to use control rods for the control of the burnup. This booklet described the concept of the CANDLE burnup strategy with basic explanations of excess neutrons and its specific application to a high-temperature gas-cooled reactor and a fast reactor with excellent neutron economy. Supplementary issues concerning the initial core and high burnup were also referred. (T. Tanaka)

  6. At What Distance Can the Human Eye Detect a Candle Flame?

    CERN Document Server

    Krisciunas, Kevin

    2015-01-01

    Using CCD observations of a candle flame situated at a distance of 338 m and calibrated with observations of Vega, we show that a candle flame situated at ~2.6 km (1.6 miles) is comparable in brightness to a 6th magnitude star with the spectral energy distribution of Vega. The human eye cannot detect a candle flame at 10 miles or further, as some statements on the web suggest.

  7. Networking of safeguards systems

    International Nuclear Information System (INIS)

    This paper discusses the design of a safeguards system that can be incorporated into a plant during the final phase of its construction to permit the acquisition and transmission of data during plant operation in the absence of an inspector. The system is an example of a networked data system of weighing, identity, and NDA information. It collects all of its non-surveillance data produced by safeguards equipment in a fuel fabrication plant. The data collection and transfer tasks are carried out by two software packages: NEGUS, a redundant data acquisition system designed to record neutron coincidence data, high-resolution gamma spectra, and sensor data for the NDA information and associated barcode identity information, and BRANCH, which deals with weighing and associated identity information. These processes collect data from local electronics using an ethernet network and provide information to the main review program

  8. IAEA Safeguards: Status and prospects

    International Nuclear Information System (INIS)

    The IAEA has just celebrated its 25th anniversary, and the first safeguards inspections were performed twenty years ago. Counting only since 1978, some 5100 inspections had been performed up to mid-1982, using a staff which now includes about 130 inspectors. Despite these impressive figures, and the fact that the IAEA has never detected any apparent diversion of nuclear materials, there are increasing public allegations that safeguards lack effectiveness. After briefly reviewing the nature of IAEA safeguards agreements, the paper examines the political and technical objectives of safeguards together with some of the criticisms which have been voiced. Allocation of limited safeguards resources is examined in terms of the sometimes conflicting allocation criteria which are contained in various safeguards documents. The paper argues that the credibility and deterrent effect of IAEA safeguards should not be underestimated. It should be of greater concern that a few States are known to be operating or constructing non-safeguarded nuclear facilities capable of producing weapons-grade nuclear materials. Thus the risk of safeguards would appear to be greatest at exactly the point where safeguards end. (author)

  9. Numerical Analysis of Flow Field in Ceramic Filter During Pulse Cleaning%陶瓷过滤器脉冲反吹系统的流场的数值模拟

    Institute of Scientific and Technical Information of China (English)

    姬忠礼; 彭书; 谭立村

    2003-01-01

    In the commercial utilization of rigid ceramic filters, the performance of pulse cleaning has crucial effects on the long-term stable operation. In order to get a clear insight into the nature of this cleaning process and provide a solid basis for industrial applications, the flow in ceramic candle filter was investigated. The flow in the pulse-jet space and inside the ceramic candle is regarded as two- dimensional, unsteady, compressible flow, and numerical simulation is carried out by computational fluid dynamics. The numerical predictions of flow field are in good agreement with the experimental measurements. Effects of the candle diameter, the separation distance between the nozzle and the candle injector and the length of the candle on the flowfield have been numerically analyzed to provide the basis for the optimum design of the pulse cleaning system.

  10. Safeguarding research reactors

    International Nuclear Information System (INIS)

    The report is organized in four sections, including the introduction. The second section contains a discussion of the characteristics and attributes of research reactors important to safeguards. In this section, research reactors are described according to their power level, if greater than 25 thermal megawatts, or according to each fuel type. This descriptive discussion includes both reactor and reactor fuel information of a generic nature, according to the following categories. 1. Research reactors with more than 25 megawatts thermal power, 2. Plate fuelled reactors, 3. Assembly fuelled reactors. 4. Research reactors fuelled with individual rods. 5. Disk fuelled reactors, and 6. Research reactors fuelled with aqueous homogeneous fuel. The third section consists of a brief discussion of general IAEA safeguards as they apply to research reactors. This section is based on IAEA safeguards implementation documents and technical reports that are used to establish Agency-State agreements and facility attachments. The fourth and last section describes inspection activities at research reactors necessary to meet Agency objectives. The scope of the activities extends to both pre and post inspection as well as the on-site inspection and includes the examination of records and reports relative to reactor operation and to receipts, shipments and certain internal transfers, periodic verification of fresh fuel, spent fuel and core fuel, activities related to containment and surveillance, and other selected activities, depending on the reactor

  11. Safeguard Vulnerability Analysis Program (SVAP)

    International Nuclear Information System (INIS)

    This report gives an overview of the Safeguard Vulnerability Analysis Program (SVAP) developed at Lawrence Livermore National Laboratory. SVAP was designed as an automated method of analyzing the safeguard systems at nuclear facilities for vulnerabilities relating to the theft or diversion of nuclear materials. SVAP addresses one class of safeguard threat: theft or diversion of nuclear materials by nonviolent insiders, acting individually or in collusion. SVAP is a user-oriented tool which uses an interactive input medium for preprocessing the large amounts of safeguards data. Its output includes concise summary data as well as detailed vulnerability information

  12. Scientific Observation and the Learning Cycle: Burning the Candle at Both Ends

    Science.gov (United States)

    Wise, Kevin; Bluhm, William J.

    2008-01-01

    This article describes a twist on the basic "Science 101" investigation of having students observe a birthday candle before, during, and after burning. It engages students in exploring the attributes of a candle, introduces them to the concepts of empirical observation and investigation, and involves them in developing and conducting a burning…

  13. On Calibrations Using the Crab Nebula as a Standard Candle

    Science.gov (United States)

    Weisskopf, Martin; Guainazzi, Matteo; Jahoda, Keith; Shaposhnikov, Nikolai; ODell, Stephen; Zavlin, Vyacheslav; Wilson-Hodge, Colleen; Elsner, Ronald

    2009-01-01

    Inspired by a recent paper (Kirsch et al. 2005) on possible use of the Crab Nebula as a standard candle for calibrating X-ray response func tions, we examine possible consequences of intrinsic departures from a single (absorbed) power law upon such calibrations. We limited our analyses to three more modern X-ray instruments -- the ROSAT/PSPC, th e RXTE/PCA, and the XMM-Newton/EPIC-pn. The results are unexpected an d indicate a need to refine two of the three response functions studi ed. The implications for Chandra will be discussed.

  14. Beam dynamics of CANDLE storage ring low alpha operation

    Science.gov (United States)

    Sargsyan, A.; Amatuni, G.; Sahakyan, V.; Tsakanov, V.; Zanyan, G.

    2015-10-01

    The generation of the coherent THz radiation and short pulse synchrotron radiation in dedicated electron storage rings requires the study of non-standard magnetic lattices which provide low momentum compaction factor (alpha) of the ring. In the present paper two low alpha operation lattices based on modification of the original beam optics and implementation of inverse bend magnets are studied for CANDLE storage ring. For considered cases an analysis of transverse and longitudinal beam dynamics is given and the feasibility of lattices is discussed.

  15. Beam dynamics of CANDLE storage ring low alpha operation

    International Nuclear Information System (INIS)

    The generation of the coherent THz radiation and short pulse synchrotron radiation in dedicated electron storage rings requires the study of non-standard magnetic lattices which provide low momentum compaction factor (alpha) of the ring. In the present paper two low alpha operation lattices based on modification of the original beam optics and implementation of inverse bend magnets are studied for CANDLE storage ring. For considered cases an analysis of transverse and longitudinal beam dynamics is given and the feasibility of lattices is discussed

  16. 75 FR 70713 - Petroleum Wax Candles From the People's Republic of China: Final Results of Expedited Third...

    Science.gov (United States)

    2010-11-18

    ... order are certain scented or unscented petroleum wax candles made from petroleum wax and having fiber or... International Trade Administration Petroleum Wax Candles From the People's Republic of China: Final Results of... petroleum wax candles from the People's Republic of China (``PRC''). On the basis of a timely notice...

  17. 75 FR 49475 - Petroleum Wax Candles From the People's Republic of China: Preliminary Results of Request for...

    Science.gov (United States)

    2010-08-13

    ... Order: Petroleum Wax Candles from the People's Republic of China, 51 FR 30686 (August 28, 1996) (``Order... scented or unscented. While manufactured in the PRC, these candles are marketed in the United States and... certain scented or unscented petroleum wax candles made from petroleum wax and having fiber or...

  18. 76 FR 46277 - Petroleum Wax Candles From the People's Republic of China: Final Results of Request for Comments...

    Science.gov (United States)

    2011-08-02

    ... Antidumping Duty Order: Petroleum Wax Candles from the People's Republic of China, 51 FR 30686 (August 28..., columns, pillars; votives; and various wax-filled containers. These candles may be scented or unscented... International Trade Administration Petroleum Wax Candles From the People's Republic of China: Final Results...

  19. 76 FR 773 - Petroleum Wax Candles From the People's Republic of China: Continuation of Antidumping Duty Order

    Science.gov (United States)

    2011-01-06

    ... a reasonably foreseeable future. See Petroleum Wax Candles From China Determination, 75 FR 80843... scented or unscented petroleum wax candles made from petroleum wax and having fiber or paper-cored wicks... International Trade Administration Petroleum Wax Candles From the People's Republic of China: Continuation...

  20. Emissions of air pollutants from scented candles burning in a test chamber

    Science.gov (United States)

    Derudi, Marco; Gelosa, Simone; Sliepcevich, Andrea; Cattaneo, Andrea; Rota, Renato; Cavallo, Domenico; Nano, Giuseppe

    2012-08-01

    Burning of scented candles in indoor environment can release a large number of toxic chemicals. However, in spite of the large market penetration of scented candles, very few works investigated their organic pollutants emissions. This paper investigates volatile organic compounds emissions, with particular reference to the priority indoor pollutants identified by the European Commission, from the burning of scented candles in a laboratory-scale test chamber. It has been found that BTEX and PAHs emission factors show large differences among different candles, possibly due to the raw paraffinic material used, while aldehydes emission factors seem more related to the presence of additives. This clearly evidences the need for simple and cheap methodologies to measure the emission factors of commercial candles in order to foresee the expected pollutant concentration in a given indoor environment and compare it with health safety standards.

  1. Intrinsic scatter of the luminosity relation, redshift distribution of the standard candles, and the constraining capability

    CERN Document Server

    Qi, Shi

    2015-01-01

    Standard candles are one of the most important tools to study the universe. In this paper, the constraints of standards candles on the cosmological parameters are estimated for different cases. The dependence of the constraints on the intrinsic scatter of the luminosity relation and the redshift distribution of the standard candles is specifically investigated. The results, especially for the constraints on the components of the universe, clearly show that constraints from standard candles at different redshifts have different degeneracy orientations, thus standard candles with a wide redshift distribution can self break the degeneracy and improve the constraints significantly. As a result of this, even with the current level of tightness of known luminosity relations, gamma-ray bursts (GRBs) can give comparable tightness of constraint with type Ia supernovae (SNe Ia) on the components of the universe as long as the redshifts of the GRBs are diversifying enough. However, for a substantial constraint on the da...

  2. Facile preparation of superhydrophobic candle soot coating and its wettability under condensation

    Science.gov (United States)

    Yuan, Zhiqing; Huang, Juan; Peng, Chaoyi; Wang, Menglei; Wang, Xian; Bin, Jiping; Xing, Suli; Xiao, Jiayu; Zeng, Jingcheng; Xiao, Ximei; Fu, Xin; Gong, Huifang; Zhao, Dejian; Chen, Hong

    2016-02-01

    A facile method was developed to prepare a superhydrophobic candle soot coating by burning candle and simple deposition on a low-density polyethylene substrate. The water contact angle and sliding angle of the as-prepared superhydrophobic candle soot coating were, respectively, 160 ± 2° and 1° under common condition. ESEM images showed that the superhydrophobic candle soot coating was comprised of many nanoparticles with the size range of about 30-50 nm. After condensation for 30 min, the average contact angle of the condensed water droplets was 150° ± 2°, showing excellent superhydrophobicity under condensation. The mechanism of the candle soot coating remaining superhydrophobicity under condensation was analyzed. This work is helpful for the design and preparation of superhydrophobic surface which can remain superhydrophobicity in future.

  3. Safeguards can not operate alone

    International Nuclear Information System (INIS)

    There are around 20 new states which are planning to use nuclear energy in the near future. Globally there are several nuclear power plants under construction and they will be bigger than ever. Also new type of nuclear facility, final disposal facility for spent nuclear fuel, will be constructed and in operation in Finland and Sweden in ca. 10 years time. It is evident that the nuclear world is changing much and quickly. After the Additional Protocol, safeguards are no longer only about accounting and control of nuclear materials, but also about verifying that there are no undeclared nuclear materials and activities in the state. It is not possible or effective anymore to implement safeguards without taking into account of the nuclear safety and security. The safeguards should not be isolated. The synergy between safeguards, security and safety exist, when implementing nationally that there are no undeclared nuclear materials or activities. In safeguards we could not do our duties effectively if we ignore some of those other S's. Safeguards by Design process does not work properly if only international safeguards and security requirements has been taken into account, it urges all 3S to be taken care at the same time. Safeguards should operate also with other synergetic regimes and organisations like CTBTO, Fissile Material Cut-off, disarmament, export control, border control,... The paper is followed by the slides of the presentation

  4. Technology Development of Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ho Dong; Kang, H. Y.; Ko, W. I. (and others)

    2007-04-15

    The objective of this project is to perform R and D on the essential technologies in nuclear material measurement and surveillance and verification system, and to improve the state of being transparent on the nuclear material management of DUPIC Fuel Development Facility (DFDF) through the evaluation of safeguard ability on non-proliferation fuel cycle and nuclear proliferation resistance. Nuclear material position scan system for the reduction of measurement error was developed for the spatial distribution search of spent fuel in DUPIC facility. Web-based realtime remote monitoring system was designed and constructed for satisfying the IAEA's performance criteria of continuous monitoring, and also developed a software for the function of remote control and message. And diversion paths in a proliferation resistant pyroprocess for SFR were analyzed and its protecting system against the diversion paths were suggested for enhancing proliferation resistance of advanced nuclear fuel cycle. These results could be used for planning the further R and D items in the area of safeguards. Those R and D results mentioned above would be helpful for increasing Korean nuclear transparency in the future.

  5. IAEA safeguards glossary. 2001 ed

    International Nuclear Information System (INIS)

    IAEA safeguards have evolved since their inception in the late 1960s. In 1980 the IAEA published the first IAEA Safeguards Glossary (IAEA/SG/INF/l) with the aim of facilitating understanding of the specialized safeguards terminology within the international community. In 1987 the IAEA published a revised edition of the Glossary (IAEA/SG/INF/l (Rev.l)) which took into account developments in the safeguards area as well as comments received since the first edition appeared. Since 1987, IAEA safeguards have become more effective and efficient, mainly through the series of strengthening measures approved by the IAEA Board of Governors during 1992-1997, the Board's approval, in 1997, of the Model Protocol Additional to the Agreement(s) between State(s) and the International Atomic Energy Agency for the Application of Safeguards (issued as INFCIRC/540 (Corrected)), and the work, begun in 1999, directed towards the development and implementation of integrated safeguards. The IAEA Safeguards Glossary 2001 Edition reflects these developments. Each of the 13 sections of the Glossary addresses a specific subject related to IAEA safeguards. To facilitate understanding. definitions and, where applicable, explanations have been given for each of the terms listed. The terms defined and explained intentionally have not been arranged in alphabetical order, but their sequence within each section corresponds to the internal relationships of the subject treated. The terms are numbered consecutively within each section and an index referring to these numbers has been provided for ease of reference. The terms used have been translated into the official languages of the IAEA, as well as into German and Japanese. The IAEA Safeguards Glossary 2001 Edition has no legal status and is not intended to serve as a basis for adjudicating on problems of definition such as might arise during the negotiation or in the interpretation of safeguards agreements or additional protocols. The IAEA

  6. IAEA safeguards glossary. 2001 ed

    International Nuclear Information System (INIS)

    IAEA safeguards have evolved since their inception in the late 1960s. In 1980 the IAEA published the first IAEA Safeguards Glossary (IAEA/SG/INF/l) with the aim of facilitating understanding of the specialized safeguards terminology within the international community. In 1987 the IAEA published a revised edition of the Glossary (IAEA/SG/INF/l (Rev.l)) which took into account developments in the safeguards area as well as comments received since the first edition appeared. Since 1987, IAEA safeguards have become more effective and efficient, mainly through the series of strengthening measures approved by the IAEA Board of Governors during 1992-1997, the Board's approval, in 1997, of the Model Protocol Additional to the Agreement(s) between State(s) and the International Atomic Energy Agency for the Application of Safeguards (issued as INFCIRC/540 (Corrected)), and the work, begun in 1999, directed towards the development and implementation of integrated safeguards. The IAEA Safeguards Glossary 2001 Edition reflects these developments. Each of the 13 sections of the Glossary addresses a specific subject related to IAEA safeguards. To facilitate understanding. definitions and, where applicable, explanations have been given for each of the terms listed. The terms defined and explained intentionally have not been arranged in alphabetical order, but their sequence within each section corresponds to the internal relationships of the subject treated. The terms are numbered consecutively within each section and an index referring to these numbers has been provided for ease of reference. The terms used have been translated into the official languages of the IAEA, as well as into German and Japanese. The IAEA Safeguards Glossary 2001 Edition has no legal status and is not intended to serve as a basis for adjudicating on problems of definition such as might arise during the negotiation or in the interpretation of safeguards agreements or additional protocols. The IAEA

  7. IAEA safeguards approaches and goals

    International Nuclear Information System (INIS)

    IAEA safeguards provide a technical means of verifying that political obligations undertaken by States party to international agreements relating to the peaceful uses of nuclear energy are being honored. The Agency assures the international community that States party to Safeguards Agreements are complying with their undertaking not to use facilities and divert nuclear materials from peaceful uses to the manufacture of nuclear explosive devices. The task of IAEA safeguards can be summed up as to detect diversion of nuclear materials committed to peaceful uses of nuclear energy, or the misuse of equipment or facilities subject to certain safeguards agreements, and to deter such diversion or misuse through the risk of early detection. This lecture concentrates on the factors the Agency takes into account in designing and implementing safeguards approaches at facilities. (author)

  8. Lifecycle Management of Safeguards Equipment

    International Nuclear Information System (INIS)

    In recent years, traditional procurement procedures for safeguards equipment have experienced major setbacks that have led to costly and time-consuming re-design and re-evaluation periods, as well as delays in the delivery and deployment of urgently needed equipment. A common element of all encountered problems is the rapid development of technical components. The accelerated pace of 69 safeguards systems development, when coupled with the absence of a disciplined lifecycle approach to design and development, leads to early technical obsolescence as well as the inability to support a safeguards system over its operational lifecycle. This condition is further aggravated by safeguards equipment suppliers who wrestle with economies of scale associated with a unique safeguards market that generally does not provide sufficient margins to stay in business. As a result, international agencies charged with safeguards responsibilities find it difficult to secure the supply of identical safeguards equipment over periods of ten or more years. However, all these problems are merely symptoms of the lack of an integrated lifecycle management approach with early involvement of all parties: vendors and their suppliers, national laboratories and contracted developers, national support programs, and international agencies with nonproliferation responsibilities. The following paper will describe the unique constellation of players within the safeguards community, and why this constellation is a cause of most of the problems inherent in traditional procurement procedures. Further, it will offer a comprehensive lifecycle management approach that will ensure the availability of identical safeguards equipment over its required lifespan (ten to fifteen years). It should be noted that an integrated lifecycle management approach will be difficult to implement and will require a fundamental re-orientation of efforts in: need identification, system design and development, funding, and

  9. Candle soot nanoparticles-polydimethylsiloxane composites for laser ultrasound transducers

    Science.gov (United States)

    Chang, Wei-Yi; Huang, Wenbin; Kim, Jinwook; Li, Sibo; Jiang, Xiaoning

    2015-10-01

    Generation of high power laser ultrasound strongly demands the advanced materials with efficient laser energy absorption, fast thermal diffusion, and large thermoelastic expansion capabilities. In this study, candle soot nanoparticles-polydimethylsiloxane (CSNPs-PDMS) composite was investigated as the functional layer for an optoacoustic transducer with high-energy conversion efficiency. The mean diameter of the collected candle soot carbon nanoparticles is about 45 nm, and the light absorption ratio at 532 nm wavelength is up to 96.24%. The prototyped CSNPs-PDMS nano-composite laser ultrasound transducer was characterized and compared with transducers using Cr-PDMS, carbon black (CB)-PDMS, and carbon nano-fiber (CNFs)-PDMS composites, respectively. Energy conversion coefficient and -6 dB frequency bandwidth of the CSNPs-PDMS composite laser ultrasound transducer were measured to be 4.41 × 10-3 and 21 MHz, respectively. The unprecedented laser ultrasound transduction performance using CSNPs-PDMS nano-composites is promising for a broad range of ultrasound therapy applications.

  10. Los Alamos safeguards program overview and NDA in safeguards

    International Nuclear Information System (INIS)

    Over the years the Los Alamos safeguards program has developed, tested, and implemented a broad range of passive and active nondestructive analysis (NDA) instruments (based on gamma and x-ray detection and neutron counting) that are now widely employed in safeguarding nuclear materials of all forms. Here very briefly, the major categories of gamma ray and neutron based NDA techniques, give some representative examples of NDA instruments currently in use, and cite a few notable instances of state-of-the-art NDA technique development. Historical aspects and a broad overview of the safeguards program are also presented

  11. Military efficacy of individual water purification filters. Technical report

    Energy Technology Data Exchange (ETDEWEB)

    Schaub, S.A.; Hargett, H.T.

    1990-12-01

    Tests were conducted to determine the effectiveness of Katadyn TM Pocket Filters (KPF) to remove enteric bacteria (Klebsiella terrigena), protozoan cysts (Cryptosporidium parvum), and cyst simulants. Studies used the U.S. Environmental Protection Agency's Guide Standard and Protocol for Testing Microbiological Purifiers for guidance. Results showed that cysts were effectively removed by the filters over a typical 100 gallon use life of the ceramic filter candles used in the KPF. Bacterial removals were shown to also meet the criteria when improvements to end seal gaskets of the ceramic filters were made.

  12. Characterization of hazardous and odorous volatiles emitted from scented candles before lighting and when lit.

    Science.gov (United States)

    Ahn, Jeong-Hyeon; Kim, Ki-Hyun; Kim, Yong-Hyun; Kim, Bo-Won

    2015-04-01

    Scented candles are known to release various volatile organic compounds (VOCs) including both pleasant aromas and toxic components both before lighting (off) and when lit (on). In this study, we explored the compositional changes of volatiles from scented candles under various settings to simulate indoor use. Carbonyl compounds and other VOCs emitted from six different candle types were analyzed under 'on/off' conditions. The six candle types investigated were: (1) Clean cotton (CT), (2) Floral (FL), (3) Kiwi melon (KW), (4) Strawberry (SB), (5) Vanilla (VN), and (6) Plain (PL). Although a large number of chemicals were released both before lighting and when lit, their profiles were noticeably distinguishable. Before lighting, various esters (n = 30) showed the most dominant emissions. When lit, formaldehyde was found to have the highest emission concentration of 2098 ppb (SB), 1022 ppb (CT), and 925 ppb (PL). In most lit scented candles, there was a general tendency to show increased concentrations of low boiling point compounds. For some scented candle products, the emission of volatiles occurred strongly both before lighting and when lit. For instance, in terms of TVOC (ppbC), the highest concentrations were observed from the KW product with their values of 12,742 (on) and 2766 ppbC (off). As such, the results suggest that certain scented candle products should act as potent sources of VOC emission in indoor environment, regardless of conditions--whether being lit or not.

  13. The next generation safeguards initiative

    International Nuclear Information System (INIS)

    NGSI or the Next Generation Safeguards Initiative is designed to revitalize the U.S. safeguards technical base, as well as invest in human resources, and to mobilize our primary asset - the U.S. National Laboratories - as well as industry and academia to restore capabilities. While NGSI is a U.S. effort it is intended to serve as a catalyst for a much broader commitment to international safeguards in partnership with the IAEA and other countries. Initiatives over the last years include such as the Proliferation Security Initiative, UN Security Council Resolution 1540, the Global Initiative to Combat Nuclear Terrorism, and initiatives of the G-8 and NSG to discourage the spread of enrichment and reprocessing. NGSI augments this agenda by providing a means to strengthen the technical and political underpinnings of IAEA safeguards. Priorities and envisioned activities under NGSI are the following. (1) Cooperation with IAEA and others to promote universal adoption of safeguards agreements and the Additional Protocol including greater information sharing between member states and the IAEA, investigation of weaponization and procurement activities, and options to strengthen the state-level approach to safeguards. (2) NGSI anticipates the deployment of new types of reactors and fuel cycle facilities, as well as the need to use limited safeguards resources effectively and efficiently, especially in plants that pose the largest burden specifically complex, bulk-handling facilities. (3) NGSI will encourage a generational improvement in current safeguards technologies including improvement of precision and speed of nuclear measurements, performance of real-time process monitoring and surveillance in unattended mode, enabling in-field, pre-screening and analysis of nuclear and environmental samples, and collection, integration, analysis and archiving safeguards-relevant information from all available sources.(4) NGSI will address human capital management. Training and

  14. Safeguards Summary Event List (SSEL)

    International Nuclear Information System (INIS)

    The Safeguards Summary Event List provides brief summaries of hundreds of safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission. Events are described under the categories: Bomb-related, Intrusion, Missing/Allegedly Stolen, Transportation-related, Tampering/Vandalism, Arson, Firearms-related, Radiological Sabotage, Non-radiological Sabotage, and Miscellaneous. Because of the public interest, the Miscellaneous category also includes events reported involving source material, byproduct material, and natural uranium, which are exempt from safeguards requirements. Information in the event descriptions was obtained from official NRC sources

  15. Safeguards summary event list (SSEL)

    International Nuclear Information System (INIS)

    The Safeguards Summary Event List (SSEL) provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission (NRC). Because of public interest, also included are events reported involving byproduct material which is exempt from safeguards requirements. Events are described under the categories of bomb-related, intrusion, missing and/or allegedly stolen, transportation, tampering/vandalism, arson, firearms, radiological sabotage, nonradiological sabotage, alcohol and drugs, and miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels

  16. Safeguards and Nuclear Material Management

    International Nuclear Information System (INIS)

    The book contains contributed papers from various authors on the following subjects: Safeguards systems and implementation, Measurement techniques: general, Measurement techniques: destructive analysis, Measurement techniques: non-destructive assay, Containment and surveillance, Spent fuel strategies, Material accounting and data evaluation

  17. Development of DUPIC safeguards technology

    Energy Technology Data Exchange (ETDEWEB)

    Kim, H. D.; Ko, W. I.; Song, D. Y. [and others

    2000-03-01

    During the first phase of R and D program conducted from 1997 to 1999, nuclear material safeguards studies system were performed on the technology development of DUPIC safeguards system such as nuclear material measurement in bulk form and product form, DUPIC fuel reactivity measurement, near-real-time accountancy, and containment and surveillance system for effective and efficient implementation of domestic and international safeguards obligation. For the nuclear material measurement system, the performance test was finished and received IAEA approval, and now is being used in DUPIC Fuel Fabrication Facility(DFDF) for nuclear material accounting and control. Other systems being developed in this study were already installed in DFDF and being under performance test. Those systems developed in this study will make a contribution not only to the effective implementation of DUPIC safeguards, but also to enhance the international confidence build-up in peaceful use of spent fuel material. (author)

  18. Reactor safeguards against insider sabotage

    Energy Technology Data Exchange (ETDEWEB)

    Bennett, H.A.

    1982-03-01

    A conceptual safeguards system is structured to show how both reactor operations and physical protection resources could be integrated to prevent release of radioactive material caused by insider sabotage. Operational recovery capabilities are addressed from the viewpoint of both detection of and response to disabled components. Physical protection capabilities for preventing insider sabotage through the application of work rules are analyzed. Recommendations for further development of safeguards system structures, operational recovery, and sabotage prevention are suggested.

  19. Safeguards Summary Event List (SSEL)

    International Nuclear Information System (INIS)

    The Safeguards Summary Event List (SSEL) provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission (NRC). Events are described under the categories of bomb-related, intrusion, missing and/or allegedly stolen, transportation, vandalism, arson, firearms, sabotage and miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels

  20. Safeguards Summary Event List (SSEL)

    International Nuclear Information System (INIS)

    The Safeguards Summary Event List (SSEL) provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the U.S. Nuclear Regulatory Commission (NRC). Events are described under the categories of bomb-related, intrusion, missing and/or allegedly stolen, transportation, tampering/vandalism, arson, firearms, radiological sabotage and miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels

  1. Safeguards Summary Event List (SSEL)

    International Nuclear Information System (INIS)

    The Safeguards Summary Event List (SSEL) provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission (NRC). Events are described under the categories of bomb-related, intrusion, missing and/or allegedly stolen, transportation, vandalism, arson, firearms, radiological sabotage and miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels

  2. Impact of small scale inhomogeneities on observations of standard candles

    CERN Document Server

    Iwata, Kengo

    2014-01-01

    We investigate the effect of small scale inhomogeneities on standard candle observations, such as type Ia supernovae (SNe) observations. Existence of the small scale inhomogeneities may cause a tension between SNe observations and other observations with larger diameter sources, such as the cosmic microwave background (CMB) observation. To clarify the impact of the small scale inhomogeneities, we use the Dyer-Roeder approach. We determined the smoothness parameter $\\alpha(z)$ as a function of the redshift $z$ so as to compensate the deviation of cosmological parameters for SNe from those for CMB. The range of the deviation which can be compensated by the smoothness parameter $\\alpha(z)$ satisfying $0\\leq\\alpha(z)\\leq1$ is reported. Our result suggests that the tension may give us the information of the small scale inhomogeneities through the smoothness parameter.

  3. Safeguards information challenges

    International Nuclear Information System (INIS)

    The purpose of this paper is to provide the background and broader vision in which the various presentations and posters on information related matters, prepared by staff of the Department of Safeguards, find their place, exploring solutions to the challenges faced. At a time when the IAEA is expected to be a reference for the assessment of nuclear proliferation issues, it faces major challenges with regard to the information needed to provide the international community with independent, impartial, timely and soundly based conclusions regarding the non-diversion of declared nuclear material and the absence of undeclared nuclear material or activities in States. The drawing of such conclusions assumes that all relevant information is accessible and has been put in the relevant context. Unfortunately, because of legal constraints under which it operates, or because of limitations on resources available for collecting existing but difficult to reach facts, or simply because of the overwhelming aspect of the information needed to properly evaluate proliferation issues, the IAEA needs to enhance the way it collects, processes, analyses, evaluates and disseminates safeguards relevant information. The search for better, broader and deeper information through dedicated collection means is an ongoing effort aimed at filling the gaps that constrain the development of the coherent picture that analysts need to be comfortable with the results of complex analyses. Implementation of well-selected information collection tools is sine qua non for effective IAEA verification capabilities. Beyond collection, the establishment of a proper information architecture and documented business processes is a prerequisite for ensuring that the available information is accessible to those with a need to know. At the same time, information must be sufficiently protected by appropriate security measures, particularly when hacking has become an intellectual sport and institutional security

  4. Mechanical behavior of ceramic composite hot-gas filters after exposure to severe environments

    Energy Technology Data Exchange (ETDEWEB)

    Pysher, D.J.; Weaver, B.L.; Smith, R.G. [Ceramic Technology Center, St. Paul, MN (United States)] [and others

    1995-08-01

    A novel type of hot-gas filter based on a ceramic fiber reinforced ceramic matrix has been developed, as reported at previous Fossil Energy Materials Conferences, through research activities at Oak Ridge National Laboratory (ORNL) and at the 3M Company. Simulated testing has been done at the Westinghouse Science and Technology Center. This filter technology has been extended to full size, 60 mm OD by 1.5 meter long candle filters and a commercially viable process for producing the filters has been developed filters are undergoing testing and demonstration use throughout the world for applications in pressurized fluidized-bed combustion (PFBC) and integrated gasification combined cycle (IGCC) plants. Demonstration tests of this ceramic composite filter along with other filters are in progress at the Tidd PFBC plant Mechanical tests were performed on the 3 M brand Ceramic Composite Candle Filter after exposure to various corrosive environments in order to assess its ability to function as a hot gas filter in coal-fired applications. Due to the different construction of ceramic composite filters and the thin composite wall versus the typical thick-walled monolithic filter, standard mechanical property tests had to be refined or modified to accurately determine the filters properties. These tests and filter property results will be described Longitudinal tensile and diametral O-ring compression tests were performed on as-produced candle filters as well as on filters which had been exposed to various environments. The exposures were for 1000 hrs at 850{degrees}C in wet air, in wet air containing Na{sub 2}CO{sub 3}, and in wet air containing NaCl. In addition, a filter which bad been coated with ash (Old Grimethorpe) was exposed to wet air at 850{degrees}C for 1000 hours.

  5. Development of Coloured Flame Candle%彩色火焰蜡烛的研制

    Institute of Scientific and Technical Information of China (English)

    王桂萍; 邓爱民; 陈维奇

    2001-01-01

    The candle with coloured flame is developed.The effect of main combustible ingredient,amount of flame-colouring ingredient and the treatment of candle wick on the generation of coloured flame is discussed.%研制了彩色火焰蜡烛.讨论了主燃剂的种类、发色剂的用量及烛芯的处理对彩焰效果的影响.

  6. Human health risk evaluation of selected VOC, SVOC and particulate emissions from scented candles.

    Science.gov (United States)

    Petry, Thomas; Vitale, Danielle; Joachim, Fred J; Smith, Ben; Cruse, Lynn; Mascarenhas, Reuben; Schneider, Scott; Singal, Madhuri

    2014-06-01

    Airborne compounds in the indoor environment arise from a wide variety of sources such as environmental tobacco smoke, heating and cooking, construction materials as well as outdoor sources. To understand the contribution of scented candles to the indoor load of airborne substances and particulate matter, candle emission testing was undertaken in environmentally controlled small and large emission chambers. Candle emission rates, calculated on the basis of measured chamber concentrations of volatile and semi-volatile organic compounds (VOC, SVOC) and particulate matter (PM), were used to predict their respective indoor air concentrations in a standard EU-based dwelling using 2 models: the widely accepted ConsExpo 1-box inhalation model and the recently developed RIFM 2-box indoor air dispersion model. The output from both models has been used to estimate more realistic consumer exposure concentrations of specific chemicals and PM in candle emissions. Potential consumer health risks associated with the candle emissions were characterized by comparing the exposure concentrations with existing indoor or ambient air quality guidelines or, where not existent, to established toxicity thresholds. On the basis of this investigation it was concluded that under normal conditions of use scented candles do not pose known health risks to the consumer.

  7. An experimental design for the investigation of water repellent property of candle soot particles

    Energy Technology Data Exchange (ETDEWEB)

    Sahoo, Bichitra Nanda; Kandasubramanian, Balasubramanian, E-mail: meetkbs@gmail.com

    2014-11-14

    The mechanistic aspect of candle soot particles under controlled atmosphere has been reported. The soot particles were characterized using Fourier transformation Infrared Spectroscopy, Raman spectroscopy, Transmission electron microscopy and X-ray diffraction. Hydrophobicity of the candle soot particles was confirmed from the presence of C–H group which enhances water repellency and can be used as filler material for fabrication of superhydrophobic coatings. The layered soot particle on the glass slide exhibits maximum water contact angle of 168°. Roughness of soot particle and various hydrophobic groups involved for obtaining superhydrophobicity were exposed. The Raman spectrum of soot particles revealed the presence of disorder graphene which was confirmed from appearance of D1 band. The agglomeration of candle soot particles has been discussed by measuring fractal dimension (D{sub f}) of the particles. The in-depth investigation for bringing the mechanism of formation of soot particle inside the flame reveals the inception of the first particles, growth of soot particles, particle coalescence, agglomeration and oxidation. Here, we have found that the mechanism of particle formation in candle flame involves various steps, in which the sintering as well as coalescence/collision process plays a major role. - Highlights: • Mechanistic aspect for hydrophobicity of candle soot is demonstrated. • Hydrophobicity of soot particles at different exposure time is described. • Agglomeration of soot particles related to fractal dimension is reported. • Mechanism of formation of soot particles in the candle flame is also described.

  8. Human health risk evaluation of selected VOC, SVOC and particulate emissions from scented candles.

    Science.gov (United States)

    Petry, Thomas; Vitale, Danielle; Joachim, Fred J; Smith, Ben; Cruse, Lynn; Mascarenhas, Reuben; Schneider, Scott; Singal, Madhuri

    2014-06-01

    Airborne compounds in the indoor environment arise from a wide variety of sources such as environmental tobacco smoke, heating and cooking, construction materials as well as outdoor sources. To understand the contribution of scented candles to the indoor load of airborne substances and particulate matter, candle emission testing was undertaken in environmentally controlled small and large emission chambers. Candle emission rates, calculated on the basis of measured chamber concentrations of volatile and semi-volatile organic compounds (VOC, SVOC) and particulate matter (PM), were used to predict their respective indoor air concentrations in a standard EU-based dwelling using 2 models: the widely accepted ConsExpo 1-box inhalation model and the recently developed RIFM 2-box indoor air dispersion model. The output from both models has been used to estimate more realistic consumer exposure concentrations of specific chemicals and PM in candle emissions. Potential consumer health risks associated with the candle emissions were characterized by comparing the exposure concentrations with existing indoor or ambient air quality guidelines or, where not existent, to established toxicity thresholds. On the basis of this investigation it was concluded that under normal conditions of use scented candles do not pose known health risks to the consumer. PMID:24582651

  9. An experimental design for the investigation of water repellent property of candle soot particles

    International Nuclear Information System (INIS)

    The mechanistic aspect of candle soot particles under controlled atmosphere has been reported. The soot particles were characterized using Fourier transformation Infrared Spectroscopy, Raman spectroscopy, Transmission electron microscopy and X-ray diffraction. Hydrophobicity of the candle soot particles was confirmed from the presence of C–H group which enhances water repellency and can be used as filler material for fabrication of superhydrophobic coatings. The layered soot particle on the glass slide exhibits maximum water contact angle of 168°. Roughness of soot particle and various hydrophobic groups involved for obtaining superhydrophobicity were exposed. The Raman spectrum of soot particles revealed the presence of disorder graphene which was confirmed from appearance of D1 band. The agglomeration of candle soot particles has been discussed by measuring fractal dimension (Df) of the particles. The in-depth investigation for bringing the mechanism of formation of soot particle inside the flame reveals the inception of the first particles, growth of soot particles, particle coalescence, agglomeration and oxidation. Here, we have found that the mechanism of particle formation in candle flame involves various steps, in which the sintering as well as coalescence/collision process plays a major role. - Highlights: • Mechanistic aspect for hydrophobicity of candle soot is demonstrated. • Hydrophobicity of soot particles at different exposure time is described. • Agglomeration of soot particles related to fractal dimension is reported. • Mechanism of formation of soot particles in the candle flame is also described

  10. Filtration efficiency of an electrostatic fibrous filter: Studying filtration dependency on ultrafine particle exposure and composition

    DEFF Research Database (Denmark)

    Ardkapan, Siamak Rahimi; Johnson, Matthew S.; Yazdi, Sadegh;

    2014-01-01

    laboratory environment using two different particle counters: a Scanning Mobility Particle Sizer and a NanoTracer. Particles were generated at different concentrations by burning a pure wax candle in a test room. The set-up consisted of a test room, a fan a duct and the particle filter. The results show...

  11. International safeguards data management system

    International Nuclear Information System (INIS)

    The data base management system ''ISADAM'' (i.e. International Safeguards Data Management System) described in this report is intended to facilitate the safeguards authority in making efficient and effective use of accounting reports. ISADAM has been developed using the ADABAS data base management system and is implemented on the JRC-Ispra computer. The evaluation of safeguards declarations focuses on three main objectives: - the requirement of syntactical consistency with the legal conventions of data recording for safeguards accountancy; - the requirement of accounting evidence that there is no material unaccounted for (MUF); - the requirement of semantic consistency with the technological characteristics of the plant and the processing plans of the operator. Section 2 describes in more detail the facilities which ISADAM makes available to a safeguards inspector. Section 3 describes how the MUF variance computation is derived from models of measurement error propagation. Many features of the ISADAM system are automatically provided by ADABAS. The exceptions to this are the utility software designed to: - screen plant declarations before loading into the data base, - prepare variance summary files designed to support real-time computation of MUF and variance of MUF, - provide analyses in response to user requests in interactive or batch mode. Section 4 describes the structure and functions of this software which have been developed by JRC-Ispra

  12. Testing of ceramic filter materials at the PCFB test facility; Keraamisten suodinmateriaalien testaus PCFB-koelaitoksessa

    Energy Technology Data Exchange (ETDEWEB)

    Kuivalainen, R.; Eriksson, T.; Lehtonen, P.; Tiensuu, J. [Foster Wheeler Energia Oy, Karhula (Finland)

    1997-10-01

    Pressurized Circulating Fluidized Bed (PCFB) combustion technology has been developed in Karhula, Finland since 1986. In 1989, a 10 MW PCFB test facility was constructed. The test facility has been used for performance testing with different coal types through the years 1990-1994 for obtaining data for design and commercialization of the high-efficiency low-emission PCFB combustion technology. The main objective of the project Y53 was to evaluate advanced candle filter materials for the Hot Gas Clean-up Unit (HGCU) to be used in a commercial PCFB Demonstration Project. To achieve this goal, the selected candle materials were exposed to actual high temperature, high pressure coal combustion flue gases for a period of 1000-1500 h during the PCFB test runs. The test runs were carried out in three test segments in Foster Wheeler`s PCFB test facility at the Karhula R and D Center. An extensive inspection and sampling program was carried out after the second test segment. Selected sample candles were analyzed by the filter supplier and the preliminary results were encouraging. The material strength had decreased only within expected range. Slight elongation of the silicon carbide candles was observed, but at this phase the elongation can not be addressed to creep, unlike in the candles tested in 1993-94. The third and last test segment was completed successfully in October 1996. The filter system was inspected and several sample candles were selected for material characterization. The results will be available in February - March 1997. (orig.)

  13. Implementing Safeguards-by-Design

    Energy Technology Data Exchange (ETDEWEB)

    Trond Bjornard; Robert Bean; Phillip Casey Durst; John Hockert; James Morgan

    2010-02-01

    Executive Summary Excerpt Safeguards-by-Design (SBD) is an approach to the design and construction of nuclear facilities whereby safeguards are designed-in from the very beginning. It is a systematic and structured approach for fully integrating international and national safeguards (MC&A), physical security, and other proliferation barriers into the design and construction process for nuclear facilities. SBD is primarily a project management or project coordination challenge, and this report focuses on that aspect of SBD. The present report continues the work begun in 2008 and focuses specifically on the design process, or project management and coordination - the planning, definition, organization, coordination, scheduling and interaction of activities of the safeguards experts and stakeholders as they participate in the design and construction of a nuclear facility. It delineates the steps in a nuclear facility design and construction project, in order to provide the project context within which the safeguards design activities take place, describes the involvement of safeguards experts in the design process, the nature of their analyses, interactions and decisions, as well as describing the documents created and how they are used. Designing and constructing a nuclear facility is an extremely complex undertaking. The stakeholders in an actual project are many – owner, operator, State regulators, nuclear facility primary contractor, subcontractors (e.g. instrument suppliers), architect engineers, project management team, safeguards, safety and security experts, in addition to the IAEA and its team. The purpose of the present report is to provide a common basis for discussions amongst stakeholders to collaboratively develop a SBD approach that will be both practically useful and mutually beneficial. The principal conclusions from the present study are: • In the short term, the successful implementation of SBD is principally a project management problem.

  14. Safeguards Summary Event List (SSEL)

    International Nuclear Information System (INIS)

    The Safeguards Summary Event List (SSEL) provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission (NRC). Because of public interest, the Miscellaneous category includes a few events which involve either source material, byproduct material, or natural uranium which are exempt from safeguards requirements. Events are described under the categories of bomb-related, intrusion, missing and/or allegedly stolen, transportation, tampering/vandalism, arson, firearms, radiological sabotage, nonradiological sabotage, pre-1990 alcohol and drugs (involving reactor operators, security force members, or management persons), and miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels

  15. Safeguards information challenges

    International Nuclear Information System (INIS)

    Full text: Overall, the aim of this paper is to provide the background and the broader vision in which the various information related presentations and posters proposed by the Department find their place, exploring solutions to the challenges faced. At a time when the Agency is expected to be a reference for the assessment of nuclear proliferation threats, providing the international community with independent, impartial, timely and credible conclusions that no declared nuclear material is diverted to non-peaceful purposes and that no undeclared nuclear material or activities exist in States, it has to address major challenges with regard to information. Drawing credible conclusions assumes that all relevant information is accessible and put into relevant context. Because of the legal constraints under which it operates, the limitation of resources for collecting existing but difficult to reach details and simply because of the overwhelming quantity of the information needed to properly evaluate proliferation issues, the Agency has to continually improve the way it collects, processes and internally disseminates safeguards relevant information. Developing a coherent picture of a State's nuclear capability is a complex process based on many experts' assessments and fusion of information. The search for better, broader and deeper information through dedicated collection processes is an ongoing effort aimed at filling the gaps of such pictures. Implementing well selected information collection tools is a sine qua non to render effective the Agency's detection capabilities. Beyond collection, another prerequisite to ensuring that the available information is accessible to those who need to know is the establishment of a proper information system architecture and an efficient set of standard business processes. At the same time, that information must be sufficiently protected by appropriate security measures, particularly at a time when private hacking has become a

  16. IAEA safeguards for the 21st century

    International Nuclear Information System (INIS)

    The publication includes the lectures held during the seminar on IAEA safeguards for the 21st century. The topics covered are as follows: the nuclear non-proliferation regime; Legal instruments related to the application of safeguards; multilateral nuclear export controls; physical protection and its role in nuclear non-proliferation; the evolution of safeguards; basis for the strengthening of safeguards; information required from states, including 'small quantities protocol'; processing and evaluation of new information for strengthened safeguards; additional physical access and new technologies for strengthened safeguards; equipping the IAEA Inspectorate with new skills; achievements to date the strengthened safeguards; complement of regional non-proliferation arrangements in international nuclear verification; promotion of transparency through Korean experience; and the future prospects of safeguards

  17. Evaluation of the efficacy of 3% citronella candles and 5% citronella incense for protection against field populations of Aedes mosquitoes.

    Science.gov (United States)

    Lindsay, L R; Surgeoner, G A; Heal, J D; Gallivan, G J

    1996-06-01

    We assessed the efficacy of 3% citronella candles and 5% citronella incense in protecting subjects from bites of Aedes spp. under field conditions. The study was conducted in a deciduous woodlot in Guelph, Ontario, Canada from July 26 to August 10, 1995. Eight subjects, dressed identically, were assigned to one of 8 positions on a grid within the study area. Two citronella candles, 2 citronella incense, 2 plain unscented candles, or no candles (i.e., nontreated controls) were assigned to 2 positions on the grid each evening. Subjects conducted 5-min biting counts at each position and performed 16 biting counts per evening. On average, subjects received 6.2 +/- 0.4, 8.2 +/- 0.5, 8.2 +/- 0.4, and 10.8 +/- 0.5 bites/ 5 min at positions with citronella candles, citronella incense, plain candles, and no candles, respectively. Although significantly fewer bites were received by subjects at positions with citronella candles and incense than at nontreated locations, the overall reduction in bites provided by the citronella candles and incense was only 42.3 and 24.2%, respectively.

  18. The psychology of nuclear safeguards

    International Nuclear Information System (INIS)

    it is argued that it is unreasonable to expect the Non-Proliferation Treaty to prevent the diversion of nuclear materials from peaceful purposes to nuclear weapons, which it was designed to do. However it is considered that although prevention cannot be guaranteed it is possible to deter such diversions. The question of publicity is examined since any safeguards system is judged exclusively on what is seen to be their failures and safeguard authorities will be tempted to conceal any diversion. (U.K.)

  19. IAEA symposium on international safeguards. Extended synopses

    International Nuclear Information System (INIS)

    The most important subjects treated in 188 papers presented by the participants from member state and IAEA Safeguards Inspectors at the Symposium were as follows: implementation of IAEA safeguards; national support programs to the IAEA safeguards; experiences in application of safeguard monitoring devices; improved methods for verification of plutonium; highly enriched uranium; surveillance of spent fuel storage facilities, reprocessing plants, fuel fabrication plants; excess weapon grade plutonium and other fissile materials

  20. Near-Infrared Hubble Diagrams and The Effectiveness of Using Type Ia Supernovae as Standard Candles In The Near-Infrared.

    Science.gov (United States)

    Gooding, Samuel D.; Hsiao, E. Y.; Marion, G. H.; Krisciunas, K.; Suntzeff, N. B.

    2009-12-01

    We use a combination of near-infrared and optical data to study the diversity in intrinsic brightness of Type Ia supernovae and to learn how better to correct for the systematic errors involved in using them as standard candles. Our sample includes light curves of 29 nearby Type Ia SNe from the Carnegie Supernova Project (CSP) at Las Campanas observatory in Chile, which observes in both optical (uBVgri) and near-IR (YJHK) filters, and other well observed nearby Type Ia SNe having light curves with both optical and near-IR data published in the literature. We also use more than forty near-IR spectra from the Marion/IRTF data set plus eleven near-IR spectra of SN 1999ee from Hamuy et al. (2002). The combined set of near-IR spectra consists of many different SNe and covers the epoch range from -13 days to +76 days with respect to V-band maximum. We are working on deriving a set of near-IR, K-corrected, and extinction-corrected YJHK light curve templates and new methods for fitting future YJHK light curve data. From observations of 20 Type Ia supernovae obtained by the CSP collaboration, along with previously published results, I will present near-IR Hubble diagrams and derived absolute magnitudes at maximum brightness for the objects that have well observed near-IR light curves. Type Ia supernovae appear to be standard candles in the near-IR to ±0.15 mag or better and there is much less extinction by dust in the near-IR compared to the optical. A better understanding of the Standard Candle nature of SNe will enable us to improve their usefulness as precise distance indicators and enter deeper into the era of precision cosmology.

  1. Applications of ''candle'' burn-up strategy to several reactors

    International Nuclear Information System (INIS)

    The new burn-up strategy CANDLE is proposed, and the calculation procedure for its equilibrium state is presented. Using this strategy, the power shape does not change as time passes, and the excess reactivity and reactivity coefficient are constant during burn-up. No control mechanism for the burn-up reactivity is required, and power control is very easy. The reactor lifetime can be prolonged by elongating the core height. This burn-up strategy can be applied to several kinds of reactors whose maximum neutron multiplication factor changes from less than unity to more than unity, and then to less than unity. In the present paper it is applied to some fast reactors, thus requiring some fissile material such as plutonium for the nuclear ignition region of the core, but only natural uranium is required for the other region of the initial reactor and for succeeding reactors. The drift speed of the burning region for this reactor is about 4 cm/year, which is a preferable value for designing a long-life reactor. The average burn-up of the spent fuel is about 40%; that is, equivalent to 40% utilisation of the natural uranium without the reprocessing and enrichment. (author)

  2. Unbiased constraints on the clumpiness of universe from standard candles

    CERN Document Server

    Li, Zhengxiang; Zhu, Zong-Hong

    2015-01-01

    We perform unbiased tests for the clumpiness of universe by confronting the Zel'dovich-Kantowski-Dyer-Roeder luminosity distance which describes the effect of local inhomogeneities on the propagation of light with the observational one estimated from measurements of standard candles, i.e., type Ia supernovae (SNe Ia) and gamma-ray bursts (GRBs). Methodologically, we first determine the light-curve fitting parameters which account for distance estimation in SNe Ia observations and luminosity/energy relations which are responsible for distance estimation of GRBs in the global fit to reconstruct the Hubble diagrams in the context of a clumpy universe. Subsequently, these Hubble diagrams allow us to achieve unbiased constraints on the matter density parameter $\\Omega_m$ as well as clumpiness parameter $\\eta$ which quantifies the fraction of homogeneously distributed matter within a given light cone. At 1$\\sigma$ confidence level, the constraints are $\\Omega_m=0.34\\pm0.02$ and $\\eta=1.00^{+0.00}_{-0.02}$ from the ...

  3. $\\gamma$-ray bursts towards a standard candle luminosity

    CERN Document Server

    Atteia, J L

    1997-01-01

    It is usual, in gamma-ray burst (GRB) studies, to compare the average properties of bright and faint GRBs, with the assumption that these brightness classes reflect distance classes. However, when brightness is intented to reflect the distance to the sources, it is important to use a quantity with a small intrinsic dispersion. We propose here a new method to compare the intrinsic dispersion of various measures of the GRB luminosity. We apply this method to GRBs in the BATSE Catalog and find that the best distance indicator in this catalog is the fluence measured below 100 keV. In general, we study the influence of the time and energy windows on the luminosity dispersion of GRBs. While we see little influence of the time window, we show that the energy window has a fundamental importance and that GRBs are much closer to standard candles below 100 keV than above. We suggest that a beaming of the emission above 100 keV could explain this behaviour.

  4. Hot-Gas Filter Ash Characterization Project

    Energy Technology Data Exchange (ETDEWEB)

    Swanson, M.L.; Hurley, J.P.; Dockter, B.A.; O`Keefe, C.A.

    1997-07-01

    Large-scale hot-gas filter testing over the past 10 years has revealed numerous cases of cake buildup on filter elements that has been difficult, if not impossible, to remove. At times, the cake can blind or bridge between candle filters, leading to filter failure. Physical factors, including particle-size distribution, particle shape, the aerodynamics of deposition, and system temperature, contribute to the difficulty in removing the cake, but chemical factors such as surface composition and gas-solid reactions also play roles in helping to bond the ash to the filters or to itself. This project is designed to perform the research necessary to determine the fuel-, sorbent-, and operations-related conditions that lead to blinding or bridging of hot-gas particle filters. The objectives of the project are threefold: (1) Determine the mechanisms by which a difficult-to-clean ash is formed and how it bridges hot-gas filters (2) Develop a method to determine the rate of bridging based on analyses of the feed coal and sorbent, filter properties, and system operating conditions and (3) Suggest and test ways to prevent filter bridging.

  5. Safeguards and non-proliferation

    International Nuclear Information System (INIS)

    It deserves re-emphasizing that the first and most important obstacle to the proliferation of nuclear weapons is a matter of political judgement and determination. Safeguards cannot prevent a violation of obligations... any more than bank or company audits can prevent a misappropriation of funds. All they can do is expose infringements or arouse suspicions - in effect, sound the alarm. By submitting the whole of their nuclear energy sector to impartial international inspection, States can inspire great confidence on the part of the rest of the world in the exclusively peaceful nature of their programmes. Safeguards are today an essential precondition for imports of nuclear power technology, uranium fuel, and many different kinds of material for the nuclear energy sector. Without IAEA safeguards, the existing market in this sector would be unworkable. Potentially, the most important aspect of the acceptance of IAEA safeguards by nuclear-weapon States is that it shows their readiness to submit important installations within their territory to impartial inspection

  6. The future for safeguards technology

    International Nuclear Information System (INIS)

    The present paper presents some elements of an emerging vision of a new and updated potential role for safeguard instrumentation in the overall process of deterring the proliferation of nuclear weapons. The paper focusses on installed, transportable and portable measurement systems and in-situ techniques for maintaining continuity of knowledge. The paper is followed by the slides of the presentation

  7. Instrument development for safeguards measurements

    Energy Technology Data Exchange (ETDEWEB)

    Zebarth, M.; Davidson, D.; Koskelo, M.; Gardner, G. [Canberra Nuclear Products Group, Meriden, CT (United States)

    1996-12-31

    New safeguards requirements, such as those resulting from industrial reprocessing activities, makes the faster and more accurate determination of the uranium enrichment and/or the isotopic composition of plutonium essential in measuring the fissile mass. In response to these needs, Canberra has developed several improved safeguards systems in the last few years. In this paper, we will present an overview of our newest safeguards systems and the improvements they contain. The portable systems include the U-Pu InSpector, the IMCA and the JSR-14 systems. All combine automatic control of acquisition electronics and rapid analysis with an integrated software package for ease of use. The U-Pu InSpector incorporates the MGA code used by the IAEA and Euratom for plutonium analysis. The IMCA complies with IAEA PMCN and PMCG procedures for uranium analysis. With the JSR-14, we are currently developing the procedures to provide compliance with the IAEA neutron counting procedures. In addition to portable safeguards systems, Canberra has designed and installed many installed systems such as the WDAS and PSMC systems at PNC Tokai in Japan, and the large unattended neutron/gamma systems at Cogema La Hague and the Melox reprocessing facility in France. (author)

  8. Safeguards Envelope Progress FY08

    Energy Technology Data Exchange (ETDEWEB)

    Robert Bean; Richard Metcalf; Aaron Bevill

    2008-09-01

    The Safeguards Envelope Project met its milestones by creating a rudimentary safeguards envelope, proving the value of the approach on a small scale, and determining the most appropriate path forward. The Idaho Chemical Processing Plant’s large cache of reprocessing process monitoring data, dubbed UBER Data, was recovered and used in the analysis. A probabilistic Z test was used on a Markov Monte Carlo simulation of expected diversion data when compared with normal operating data. The data regarding a fully transient event in a tank was used to create a simple requirement, representative of a safeguards envelope, whose impact was a decrease in operating efficiency by 1.3% but an increase in material balance period of 26%. This approach is operator, state, and international safeguards friendly and should be applied to future reprocessing plants. Future requirements include tank-to-tank correlations in reprocessing facilities, detailed operations impact studies, simulation inclusion, automated optimization, advanced statistics analysis, and multi-attribute utility analysis.

  9. Instrument development for safeguards measurements

    International Nuclear Information System (INIS)

    New safeguards requirements, such as those resulting from industrial reprocessing activities, makes the faster and more accurate determination of the uranium enrichment and/or the isotopic composition of plutonium essential in measuring the fissile mass. In response to these needs, Canberra has developed several improved safeguards systems in the last few years. In this paper, we will present an overview of our newest safeguards systems and the improvements they contain. The portable systems include the U-Pu InSpector, the IMCA and the JSR-14 systems. All combine automatic control of acquisition electronics and rapid analysis with an integrated software package for ease of use. The U-Pu InSpector incorporates the MGA code used by the IAEA and Euratom for plutonium analysis. The IMCA complies with IAEA PMCN and PMCG procedures for uranium analysis. With the JSR-14, we are currently developing the procedures to provide compliance with the IAEA neutron counting procedures. In addition to portable safeguards systems, Canberra has designed and installed many installed systems such as the WDAS and PSMC systems at PNC Tokai in Japan, and the large unattended neutron/gamma systems at Cogema La Hague and the Melox reprocessing facility in France. (author)

  10. Nuclear safeguards and physical protection

    International Nuclear Information System (INIS)

    In the present lecture two topics are covered: 1) the steps or the infrastructure which the operators of a nuclear facility have to foresee for the implementation of safeguards according to the NPT. 2) General features of a national physical protection system for nuclear materials in use, storage and transport. (orig./RW)

  11. Safeguards against Takeover after Volkswagen

    DEFF Research Database (Denmark)

    Werlauff, Erik

    2009-01-01

    The article analyses the significance of the European Court's decision on the effects of the rules on the free movement of capital on the takeover safeguards in Volkswagen AG for restrictions on the right to vote, ownership ceilings, division into A and B share classes, increased majority...

  12. Process Monitoring for Nuclear Safeguards

    International Nuclear Information System (INIS)

    Process Monitoring has long been used to evaluate industrial processes and operating conditions in nuclear and non-nuclear facilities. In nuclear applications there is a recognized need to demonstrate the safeguards benefits from using advanced process monitoring on spent fuel reprocessing technologies and associated facilities, as a complement to nuclear materials accounting. This can be accomplished by: defining credible diversion pathway scenarios as a sample problem; using advanced sensor and data analysis techniques to illustrate detection capabilities; and formulating 'event detection' methodologies as a means to quantify performance of the safeguards system. Over the past 30 years there have been rapid advances and improvement in the technology associated with monitoring and control of industrial processes. In the context of bulk handling facilities that process nuclear materials, modern technology can provide more timely information on the location and movement of nuclear material to help develop more effective safeguards. For international safeguards, inspection means verification of material balance data as reported by the operator through the State to the international inspectorate agency. This verification recognizes that the State may be in collusion with the operator to hide clandestine activities, potentially during abnormal process conditions with falsification of data to mask the removal. Records provided may show material is accounted for even though a removal occurred. Process monitoring can offer additional fidelity during a wide variety of operating conditions to help verify the declaration or identify possible diversions. The challenge is how to use modern technology for process monitoring and control in a proprietary operating environment subject to safeguards inspectorate or other regulatory oversight. Under the U.S. National Nuclear Security Administration's Next Generation Safeguards Initiative, a range of potential safeguards applications

  13. Inspection technologies -Development of national safeguards technology-

    International Nuclear Information System (INIS)

    17 facility regulations prepared by nuclear facilities according to the Ministerial Notices were evaluated. Safeguards inspection activities under Safeguards are described. Safeguards inspection equipments and operation manuals to be used for national inspection are also described. Safeguards report are produced and submitted to MOST by using the computerized nuclear material accounting system at state level. National inspection support system are developed to produce the on-site information for domestic inspection. Planning and establishment of policy for nuclear control of nuclear materials, international cooperation for nuclear control, CTBT, strengthening of international safeguards system, and the supply of PWRs to North Korea are also described. (author). 43 tabs., 39 figs

  14. UKAEA Safeguards R and D Project

    International Nuclear Information System (INIS)

    This is the fifth report of work being carried out in the UK on Safeguards R and D in support of the IAEA. The tasks included in the current UK Safeguards R and D Programme cover a wide diversity of aspects in the Safeguards field, with the work on them being conducted at several locations within the UK. It is convenient to classify the tasks as follows: reprocessing and centrifuge enrichment plant safeguards, general application of safeguards (tasks concerned with the development of instruments and techniques for general application), service programmes (tasks which are of service to the IAEA, eg calibration, training courses) and exploratory and short term tasks. (U.K.)

  15. Safeguards instrumentation: a computer-based catalog

    International Nuclear Information System (INIS)

    The information contained in this catalog is needed to provide a data base for safeguards studies and to help establish criteria and procedures for international safeguards for nuclear materials and facilities. The catalog primarily presents information on new safeguards equipment. It also describes entire safeguards systems for certain facilities, but it does not describe the inspection procedures. Because IAEA safeguards do not include physical security, devices for physical protection (as opposed to containment and surveillance) are not included. An attempt has been made to list capital costs, annual maintenance costs, replacement costs, and useful lifetime for the equipment. For equipment which is commercially available, representative sources have been listed whenever available

  16. ELECTROSTATICALLY ENHANCED BARRIER FILTER COLLECTION

    Energy Technology Data Exchange (ETDEWEB)

    John Erjavec; Michael D. Mann; Ryan Z. Knutson; Michael L. Swanson; Michael E. Collings

    2003-06-01

    electrostatically enhanced barrier filter collection (EBFC). This concept combines electrostatic precipitation (ESP) with candle filters in a single unit. Similar technology has been recently proven on a commercial scale for atmospheric applications, but needed to be tested at high temperatures and pressures. The synergy obtained by combining the two control technologies into a single system should actually reduce filter system capital and operating costs and make the system more reliable. More specifically, the ESP is expected to significantly reduce candle filter load and also to limit ash reintrainment, allowing for full recovery of baseline pressure drop during backpulsing of the filters.

  17. 16 CFR Table 2 to Part 1512 - Minimum Candlepower per Incident Foot-Candle for Clear Reflector 1

    Science.gov (United States)

    2010-01-01

    ... 16 Commercial Practices 2 2010-01-01 2010-01-01 false Minimum Candlepower per Incident Foot-Candle for Clear Reflector 1 2 Table 2 to Part 1512 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION... 1512—Minimum Candlepower per Incident Foot-Candle for Clear Reflector 1 Observation angle Front,...

  18. 16 CFR Table 1 to Part 1512 - Minimum Candlepower per Incident Foot-Candle for Clear Reflector 1

    Science.gov (United States)

    2010-01-01

    ... 16 Commercial Practices 2 2010-01-01 2010-01-01 false Minimum Candlepower per Incident Foot-Candle for Clear Reflector 1 1 Table 1 to Part 1512 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION... 1512—Minimum Candlepower per Incident Foot-Candle for Clear Reflector 1 Observation angle Front,...

  19. Visualizing Safeguards: Software for Conceptualizing and Communicating Safeguards Data

    Energy Technology Data Exchange (ETDEWEB)

    Gallucci, N. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2015-07-12

    The nuclear programs of states are complex and varied, comprising a wide range of fuel cycles and facilities. Also varied are the types and terms of states’ safeguards agreements with the IAEA, each placing different limits on the inspectorate’s access to these facilities. Such nuances make it difficult to draw policy significance from the ground-level nuclear activities of states, or to attribute ground-level outcomes to the implementation of specific policies or initiatives. While acquiring a firm understanding of these relationships is critical to evaluating and formulating effective policy, doing so requires collecting and synthesizing large bodies of information. Maintaining a comprehensive working knowledge of the facilities comprising even a single state’s nuclear program poses a challenge, yet marrying this information with relevant safeguards and verification information is more challenging still. To facilitate this task, Brookhaven National Laboratory has developed a means of capturing the development, operation, and safeguards history of all the facilities comprising a state’s nuclear program in a single graphic. The resulting visualization offers a useful reference tool to policymakers and analysts alike, providing a chronology of states’ nuclear development and an easily digestible history of verification activities across their fuel cycles.

  20. Safeguards instrumentation: past, present, future

    International Nuclear Information System (INIS)

    Instruments are essential for accounting, for surveillance and for protection of nuclear materials. The development and application of such instrumentation is reviewed, with special attention to international safeguards applications. Active and passive nondestructive assay techniques are some 25 years of age. The important advances have been in learning how to use them effectively for specific applications, accompanied by major advances in radiation detectors, electronics, and, more recently, in mini-computers. The progress in seals has been disappointingly slow. Surveillance cameras have been widely used for many applications other than safeguards. The revolution in TV technology will have important implications. More sophisticated containment/surveillance equipment is being developed but has yet to be exploited. On the basis of this history, some expectations for instrumentation in the near future are presented

  1. Simulation Enabled Safeguards Assessment Methodology

    Energy Technology Data Exchange (ETDEWEB)

    Robert Bean; Trond Bjornard; Thomas Larson

    2007-09-01

    It is expected that nuclear energy will be a significant component of future supplies. New facilities, operating under a strengthened international nonproliferation regime will be needed. There is good reason to believe virtual engineering applied to the facility design, as well as to the safeguards system design will reduce total project cost and improve efficiency in the design cycle. Simulation Enabled Safeguards Assessment MEthodology (SESAME) has been developed as a software package to provide this capability for nuclear reprocessing facilities. The software architecture is specifically designed for distributed computing, collaborative design efforts, and modular construction to allow step improvements in functionality. Drag and drop wireframe construction allows the user to select the desired components from a component warehouse, render the system for 3D visualization, and, linked to a set of physics libraries and/or computational codes, conduct process evaluations of the system they have designed.

  2. Safeguards issues in spent fuel consolidation facilities

    Energy Technology Data Exchange (ETDEWEB)

    Belew, W.L.; Moran, B.W.

    1991-01-01

    In the nuclear power industry, the fuel assembly is the basic unit for nuclear material accountancy. The safeguards procedures for the spent fuel assemblies, therefore, are based on an item accountancy approach. When fuel consolidation occurs in at-reactor'' or away-from-reactor'' facilities, the fuel assemblies are disassembled and cease to be the basic unit containing nuclear material. Safeguards can no longer be based on item accountancy of fuel assemblies. The spent fuel pins containing plutonium are accessible, and the possibilities for diversion of spent fuel for clandestine reprocessing to recover the plutonium are increased. Thus, identifying the potential safeguards concerns created by operation of these facilities is necessary. Potential safeguards techniques to address these concerns also must be identified so facility designs may include the equipment and systems required to provide an acceptable level of assurance that the international safeguards objectives can be met when these facilities come on-line. The objectives of this report are (1) to identify the safeguards issues associated with operation of spent fuel consolidation facilities, (2) to provide a preliminary assessment of the assessment of the safeguards vulnerabilities introduced, and (3) to identify potential safeguards approaches that could meet international safeguards requirements. The safeguards aspects of spent fuel consolidation are addressed in several recent reports and papers. 11 refs., 3 figs., 3 tabs.

  3. Safeguards from the operators viewpoint

    International Nuclear Information System (INIS)

    Since its inception as a nuclear materials processing facility, nuclear materials accounting has been an integral part of process operations at Los Alamos. Accountability practices have been improved from largely destructive assay in 1950 to resolve inventory differences to heavy reliance on NDA today. Much of the NDA development at the plutonium processing facility has been made possible by a close physical and working relationship with the safeguards research and development personnel

  4. Environment and Safeguards Compliance Policy

    OpenAIRE

    Inter-American Development Bank (IDB)

    2006-01-01

    This Environment and Safeguards Compliance Policy was approved by the IDB's Board of Executive Directors on January 19, 2006. It supersedes the Bank's previous environment policy, which dated to 1979, and reinforces the environmental mandates of the Eighth Capital Replenishment. The new Policy strengthens the Bank's commitment with environmental sustainability in the region. This Policy consists of a set of directives that will guide the Bank's work towards environmental sustainability throug...

  5. Designing Data Protection Safeguards Ethically

    OpenAIRE

    Ugo Pagallo

    2011-01-01

    Since the mid 1990s, lawmakers and scholars have worked on the idea of embedding data protection safeguards in information and communication technology (ICT) with the aim to access and control personal data in compliance with current regulatory frameworks. This effort has been strengthened by the capacities of computers to draw upon the tools of artificial intelligence (AI) and operations research. However, work on AI and the law entails crucial ethical issues concerning both values and modal...

  6. Safeguards Envelope Progress FY10

    Energy Technology Data Exchange (ETDEWEB)

    Richard Metcalf

    2010-10-01

    The Safeguards Envelope is a strategy to determine a set of specific operating parameters within which nuclear facilities may operate to maximize safeguards effectiveness without sacrificing safety or plant efficiency. This paper details the additions to the advanced operating techniques that will be applied to real plant process monitoring (PM) data from the Idaho Chemical Processing Plant (ICPP). Research this year focused on combining disparate pieces of data together to maximize operating time with minimal downtime due to safeguards. A Chi-Square and Croiser's cumulative sum were both included as part of the new analysis. Because of a major issue with the original data, the implementation of the two new tests did not add to the existing set of tests, though limited one-variable optimization made a small increase in detection probability. Additional analysis was performed to determine if prior analysis would have caused a major security or safety operating envelope issue. It was determined that a safety issue would have resulted from the prior research, but that the security may have been increased under certain conditions.

  7. Are xenotransplantation safeguards legally viable?

    Science.gov (United States)

    Florencio, P S; Ramanathan, E D

    2001-01-01

    Scientists agree on the need for robust public health safeguards to accompany the imminent introduction of xenotransplantation--clinical transplantation of animal tissue into humans. To protect society in the event of emerging infectious diseases, governments must devise a legally effective means of ensuring compliance with such safeguards. Neither consent law, the law of contracts, nor existing public health legislation can adequately enforce such compliance. Consent law serves as a mechanism of communicating the momentary waiver of legal rights, not as a durable enforcement doctrine. Because it would be essential for recipients personally to comply with public safety measures, the law of contracts would also be unable to compel compliance. Existing public health legislation would also likely be ineffective because it would need to be substantially amended to incorporate the heightened powers necessary for the periodic examination of asymptomatic xenotransplant recipients. Xenotransplantation-specific legislation would be a legally effective means of enforcing public health safeguards since it could require conforming behaviors and could impose monetary fines on those recipients who, having benefited from life-saving intervention, fail to comply. This Article argues that legislation implementing a post-xenotransplantation surveillance system should withstand constitutional scrutiny because it would not be discriminatory and because, although it would violate fundamental rights of recipients, such violations would be justified under existing constitutional doctrines. PMID:15212014

  8. Safeguards Indexing Method for the Regulatory Assessment of Safeguards Culture at Nuclear Facilities

    International Nuclear Information System (INIS)

    The Hungarian Atomic Energy Authority (HAEA) has just introduced a safeguards indexing method for evaluation the safeguards culture at Hungarian nuclear facilities. The main goal of this indexing method is to provide a useful tool for the regulatory body to evaluate the safeguards culture at nuclear facilities. The evaluated parameters are e.g. educational requirement for safeguards staff, quality of safeguards reporting for IAEA and EC, results of safeguards inspections etc. Input of the method is for the one hand the outcome of the comprehensive domestic safeguards verification system consisting of regular comprehensive SSAC verifications of the facilities. The main goals of the comprehensive verification system are: (1) to assess the facilities safeguards system compliance with the relevant national legislation and recommendations, (2) to assess the activities of the facility aimed at maintaining and further developing its safeguards system and (3) to revise validity of data and information previously provided by the facility subject to safeguards licensing procedures. On the other hand the annual report of the nuclear facilities also supports the safeguards indexing method, which is a good indicator of the present and future effectiveness of the facility level safeguards system and the level of safeguards culture.

  9. DEVELOPMENT AND TESTING OF A CERIA-ZIRCONIA TOUGHENED ALUMINA PROTOTYPE FILTER ELEMENT MADE OF RETICULATED CERAMIC FOAM COATED WITH A CERAMIC MEMBRANE ACTING AS BARRIER FILTER FOR FLY ASH

    Energy Technology Data Exchange (ETDEWEB)

    Guilio A. Rossi; Kenneth R. Butcher; Stacia M. Wagner

    1999-02-19

    The objective of this work was to fabricate subscale candle filters using a Ce-ZTA reticulated foam material. Specifically Selee fabricated 60mm diameter cylinders with one closed end and one flanged end. Selee Corporation developed a small pore size (5-10 {micro}m) filtration membrane which was applied to the reticulated foam surface to provide a barrier filter surface. The specific tasks to be performed were as follows: (Task 1) Filter Element Development--To fabricate subscale filter elements from zirconia toughened alumina using the reticulated foam manufacturing process. The filter elements were required to meet dimensional tolerances specified by an appropriate filter system supplier. The subscale filter elements were fabricated with integral flanges and end caps, that is, with no glued joints. (Task 2) Membrane Development--To develop a small pore filtration membrane that is to be applied to the reticulated foam material. This membrane was to provide filtration characteristics that meet gas turbine requirements and pressure drop or permeability requirements specified by the filter system supplier. (Task 3) Subscale Filter Element Fabrication--To fabricate six subscale filter elements with integral flanges and closed ends, as well as fine pore size filtration membranes. Three filters were to have a central clean gas channel, while three would have no central channel. The filters were to be provided to FETC for testing in laboratory systems or pilot scale exposure systems as appropriate. The candles were to meet dimensional tolerances as provided by filter system suppliers.

  10. Superluminous Supernovae as Standardizable Candles and High-redshift Distance Probes

    Science.gov (United States)

    Inserra, C.; Smartt, S. J.

    2014-12-01

    We investigate the use of type Ic superluminous supernovae (SLSN Ic) as standardizable candles and distance indicators. Their appeal as cosmological probes stems from their remarkable peak luminosities, hot blackbody temperatures, and bright rest-frame ultraviolet emission. We present a sample of 16 published SLSN, from redshifts 0.1 to 1.2, and calculate accurate K corrections to determine uniform magnitudes in 2 synthetic rest-frame filter bandpasses with central wavelengths at 400 nm and 520 nm. At 400 nm, we find an encouragingly low scatter in their uncorrected, raw mean magnitudes with M(400) = -21.86 ± 0.35 mag for the full sample of 16 objects. We investigate the correlation between their decline rates and peak magnitude and find that the brighter events appear to decline more slowly. In a manner similar to the Phillips relation for type Ia SNe (SNe Ia), we define a ΔM 20 decline relation. This correlates peak magnitude and decline over 20 days and can reduce the scatter in standardized peak magnitudes to ±0.22 mag. We further show that M(400) appears to have a strong color dependence. Redder objects are fainter and also become redder faster. Using this peak magnitudecolor evolution relation, a surprisingly low scatter of between ±0.08 mag and ±0.13 mag can be found in peak magnitudes, depending on sample selection. However, we caution that only 8 to 10 objects currently have enough data to test this peak magnitudecolor evolution relation. We conclude that SLSN Ic are promising distance indicators in the high-redshift universe in regimes beyond those possible with SNe Ia. Although the empirical relationships are encouraging, the unknown progenitor systems, how they may evolve with redshift, and the uncertain explosion physics are of some concern. The two major measurement uncertainties are the limited numbers of low-redshift, well-studied objects available to test these relationships and internal dust extinction in the host galaxies.

  11. 21 CFR 26.21 - Safeguard clause.

    Science.gov (United States)

    2010-04-01

    ... OF PHARMACEUTICAL GOOD MANUFACTURING PRACTICE REPORTS, MEDICAL DEVICE QUALITY SYSTEM AUDIT REPORTS... Specific Sector Provisions for Pharmaceutical Good Manufacturing Practices § 26.21 Safeguard clause....

  12. Experiences and prospects of safeguards in PNC

    International Nuclear Information System (INIS)

    The Power Reactor and Nuclear Fuel Development Corporation (PNC) initiated nuclear safeguards activities in 1960. In 1965, PNC developed a nuclear material accounting system for the handling of plutonium. A participant in IAEA inspections since 1968, PNC enacted the nuclear safeguards provisions of the Treaty on the Non-Proliferation of Nuclear Weapons in 1977. By that time, the methods and equipment used in the IAEA inspections were similar to those used today. New Safeguards Concepts for Peaceful Uses of Nuclear Material, which Japan and the USA will sign shortly, clearly states that information on relevant safeguard features shall be supplied to the IAEA on a voluntary basis, starting from the early design stages of the facility. The information will permit the IAEA to identify the key techniques and measures needed to implement the relevant safeguard provisions agreed to between Japan and the USA. In compliance with the Safeguards Concepts, work is proceeding on the relevant safeguard provisions for the Plutonium Fuel Production Facility and MONJU. PNC's nuclear safeguards experience should prove useful in developing the safeguard provisions for new R and D programs and facilities. (author)

  13. International acceptability of advanced safeguarding techniques

    International Nuclear Information System (INIS)

    There are active development programs now under way to significantly enhance the effectiveness of international safeguarding. Advanced safeguarding techniques now under development include new material accounting methods utilizing nondestructive assay techniques, more reliable surveillance instrumentation, tamper-resistant and tamper-indicating seals, new means of utilizing continuous human inspection, and systems that incorporate both passive and active use-denial technologies. Before these new safeguarding techniques are utilized, however, they must be acceptable to the international community. This will unquestionably result in a compromise between what is technically feasible and what is politically acceptable. This report highlights many of the elements common to advanced safeguarding techniques that impact directly upon international acceptability. The concept of acceptability is viewed from the perspective of three different groups: (1) those States seeking upgraded safeguards, (2) those States having safeguards imposed upon them, and (3) the International Atomic Energy Agency. In general, a more conducive climate exists today for the acceptance of advanced safeguarding techniques than at any period in the past; but the differences between advanced safeguards and those safeguards being employed today are so large that considerable opposition to their implementation can be expected

  14. The basis for the strengthening of safeguards

    International Nuclear Information System (INIS)

    For the past 30 years, the International Atomic Energy Agency's safeguards system has contributed to the international non-proliferation regime, by providing, inter alia, assurances regarding the peaceful uses of declared nuclear material. However, the discovery of a clandestine nuclear weapons programme in Iraq in 1991 drew world-wide attention to the need to strengthen the system to address the absence of undeclared nuclear material and activities. Efforts to strengthen the IAEA's safeguards system began in 1991 and culminated in 1997 when the IAEA's Board of Governors approved a Model Protocol Additional to IAEA Safeguards Agreements which greatly expands the legal basis and scope of IAEA safeguards. Within this strengthened system it is expected that the IAEA be able to provide assurance not only of the absence of diversion of declared nuclear material but also on the absence of undeclared nuclear material and activities. This is to be done within a safeguards system that uses an optimal combination of all safeguards measures available, thereby achieving maximum effectiveness and efficiency within the available resources. This paper will summarize the evolution of the safeguards system, describe strengthened safeguards, report on the status of implementing the strengthening measures, and outline plans for integrating all available safeguards measures. (author)

  15. IAEA safeguards: Staying ahead of the game

    International Nuclear Information System (INIS)

    What are nuclear safeguards and why are they important? Answers are provided in the booklet, describing and explaining the fundamentals of the IAEA safeguards system and its role as a key element of international security, and addressing the system's implementation, costs, requirements, resources and historical development, with an emphasis on trends and strengthening measures over the past 10-15 years. Topics discussed include the safeguards State evaluation process and and the key requirements of the safeguards system including information sources (open source information, commercial satellite imagery and nuclear trade related information) and the state of the art equipment, techniques and technology (unattended and remote monitoring equipment, environmental sampling, etc.)

  16. Skin contact transfer of three fragrance residues from candles to human hands.

    Science.gov (United States)

    Api, Anne Marie; Bredbenner, Amy; McGowen, Margaret; Niemiera, David; Parker, Lori; Renskers, Kevin; Selim, Sami; Sgaramella, Richard; Signorelli, Richard; Tedrow, Sebastian; Troy, William

    2007-08-01

    The dermal hand transfer of three fragrance materials (cinnamic aldehyde, d-limonene and eugenol) from scented candles was determined in 10 subjects (i.e., 20 hands) after grasping scented candles for 5 consecutive 20s exposures/grasps. The fragrance materials from each subject's hands were recovered by isopropyl alcohol wipes and subsequent extractions. Removal efficiencies for both cinnamic aldehyde and eugenol placed directly on the hands were not concentration dependent and ranged from 103% to 106%. The removal efficiency of d-limonene showed an inverse relation with 74.3% removed at the low concentration of 50 microg and 63.8% removed at the high concentration of 500 microg. The residue/transfer of d-limonene from the candles to the hands was below the limit of detection of 50 microg. The residue/transfer of cinnamic aldehyde and eugenol to each subject's hands was consistent between subjects as well as between each exposure/grasp. The total mean residues of cinnamic aldehyde and eugenol transferred per grasp from the candles to the hands were 0.255 microg/cm(2) and 0.279 microg/cm(2), respectively.

  17. Burning a Candle in a Vessel, a Simple Experiment with a Long History

    Science.gov (United States)

    Vera, Francisco; Rivera, Rodrigo; Nunez, Cesar

    2011-01-01

    The experiment in which a candle is burned inside an inverted vessel partially immersed in water has a history of more than 2,200 years, but even nowadays it is common that students and teachers relate the change in volume of the enclosed air to its oxygen content. Contrary to what many people think, Lavoisier concluded that any change in volume…

  18. CANDLES AND INCENSE AS POTENTIAL SOURCES OF INDOOR AIR POLLUTION: MARKET ANALYSIS AND LITERATURE SEARCH

    Science.gov (United States)

    The report summarizes available information on candles and incense as potential sources of indoor air pollution. It covers market information and a review of the scientific literature. The market information collected focuses on production and sales data, typical uses in the U.S....

  19. ANALYSIS OF LEAD IN CANDLE PARTICULATE EMISSIONS BY XRF USING UNIQUANT 4

    Science.gov (United States)

    As part of an extensive program to study the small combustion sources of indoor fine particulate matter (PM), candles with lead-core wicks were burned in a 46-L glass flow- through chamber. The particulate emissions with aerodynamic diameters <10 micrometers (PM10) were captured ...

  20. Hansa Candle viib küünlad Moskvasse / Väinu Rozental

    Index Scriptorium Estoniae

    Rozental, Väinu, 1957-

    2006-01-01

    Ilmunud ka: Delovõje Vedomosti 29. märts lk. 4. AS Hansa Candle paneb Viljandi tootmishoone liinid üles Moskva lähistele, et oma toodanguga jõuda Venemaa turule. Diagramm: Majandusnäitajad. Vt. samas: Küünlatehas otsib parafiinist odavamat tooret

  1. The Candle Scheme for Creating an on-line Computer Science Program - Experiences and Vision

    Directory of Open Access Journals (Sweden)

    Erkki SUTINEN

    2003-04-01

    Full Text Available Distance learning programs have rapidly increased during the past few decades. In fall 2000 the University of Joensuu started to offer distance Computer Science (CS studies to the high school students in surrounding rural areas of Joensuu. In this program high school students study the first year's university level CS studies over the web simultaneously with their regular high school studies. We describe the creation process of our virtual curriculum which is based the so-called Candle scheme. The Candle scheme search the most essential principles needed in on-line course design, supporting a student locally in her authentic learning needs via electronic tools in a light way. With the Candle scheme we have successfully focused in our design process on the most essential parts of the virtual study process. Our experiences of the Candle scheme in the creation process of the on-line CS program during years 2000-2002 indicate that the scheme is the functional one and expandable to other contexts as well.

  2. Verification and the safeguards legacy

    International Nuclear Information System (INIS)

    A number of inspection or monitoring systems throughout the world over the last decades have been structured drawing upon the IAEA experience of setting up and operating its safeguards system. The first global verification system was born with the creation of the IAEA safeguards system, about 35 years ago. With the conclusion of the NPT in 1968, inspections were to be performed under safeguards agreements, concluded directly between the IAEA and non-nuclear weapon states parties to the Treaty. The IAEA developed the safeguards system within the limitations reflected in the Blue Book (INFCIRC 153), such as limitations of routine access by the inspectors to 'strategic points', including 'key measurement points', and the focusing of verification on declared nuclear material in declared installations. The system, based as it was on nuclear material accountancy. It was expected to detect a diversion of nuclear material with a high probability and within a given time and therefore determine also that there had been no diversion of nuclear material from peaceful purposes. The most vital element of any verification system is the inspector. Technology can assist but cannot replace the inspector in the field. Their experience, knowledge, intuition and initiative are invaluable factors contributing to the success of any inspection regime. The IAEA inspectors are however not part of an international police force that will intervene to prevent a violation taking place. To be credible they should be technically qualified with substantial experience in industry or in research and development before they are recruited. An extensive training program has to make sure that the inspectors retain their professional capabilities and that it provides them with new skills. Over the years, the inspectors and through them the safeguards verification system gained experience in: organization and management of large teams; examination of records and evaluation of material balances

  3. ADVANCED HOT GAS FILTER DEVELOPMENT

    Energy Technology Data Exchange (ETDEWEB)

    E.S. Connolly; G.D. Forsythe

    1998-12-22

    Advanced, coal-based power plants will require durable and reliable hot gas filtration systems to remove particulate contaminants from the gas streams to protect downstream components such as turbine blades from erosion damage. It is expected that the filter elements in these systems will have to be made of ceramic materials to withstand goal service temperatures of 1600 F or higher. Recent demonstration projects and pilot plant tests have indicated that the current generation of ceramic hot gas filters (cross-flow and candle configurations) are failing prematurely. Two of the most promising materials that have been extensively evaluated are clay-bonded silicon carbide and alumina-mullite porous monoliths. These candidates, however, have been found to suffer progressive thermal shock fatigue damage, as a result of rapid cooling/heating cycles. Such temperature changes occur when the hot filters are back-pulsed with cooler gas to clean them, or in process upset conditions, where even larger gas temperature changes may occur quickly and unpredictably. In addition, the clay-bonded silicon carbide materials are susceptible to chemical attack of the glassy binder phase that holds the SiC particles together, resulting in softening, strength loss, creep, and eventual failure.

  4. A five-year performance review of field-scale, slow-release permanganate candles with recommendations for second-generation improvements.

    Science.gov (United States)

    Christenson, Mark; Kambhu, Ann; Reece, James; Comfort, Steve; Brunner, Laurie

    2016-05-01

    In 2009, we identified a TCE plume at an abandoned landfill that was located in a low permeable silty-clay aquifer. To treat the TCE, we manufactured slow-release potassium permanganate cylinders (oxidant candles) that had diameters of either 5.1 or 7.6 cm and were 91.4 cm long. In 2010, we compared two methods of candle installation by inserting equal masses of the oxidant candles (7.6-cm vs 5.1-cm dia). The 5.1-cm dia candles were inserted with direct-push rods while the 7.6-cm candles were housed in screens and lowered into 10 permanent wells. Since installation, the 7.6-cm oxidant candles have been refurbished approximately once per year by gently scraping off surface oxides. In 2012, we reported initial results; in this paper, we provide a 5-yr performance review since installation. Temporal sampling shows oxidant candles placed in wells have steadily reduced migrating TCE concentrations. Moreover, these candles still maintain an inner core of oxidant that has yet to contribute to the dissolution front and should provide several more years of service. Oxidant candles inserted by direct-push have stopped reducing TCE concentrations because a MnO2 scale developed on the outside of the candles. To counteract oxide scaling, we fabricated a second generation of oxidant candles that contain sodium hexametaphosphate. Laboratory experiments (batch and flow-through) show that these second-generation permanganate candles have better release characteristics and are less prone to oxide scaling. This improvement should reduce the need to perform maintenance on candles placed in wells and provide greater longevity for candles inserted by direct-push. PMID:26901481

  5. Network technology for safeguards applications

    International Nuclear Information System (INIS)

    A new flexible technology is now available to design sensor and control networks based on a protocol embedded in an intelligent communications integrated circuit. The flexibility allows a system designer and/or a technical installer to make appropriate tradeoffs between simplicity, functionality, and cost in the design of network nodes and their installation. This is especially important in designing the installation scenario for the safeguards network. The network technology permits several choices of installations with the same basic mode hardware. This paper is a discussion of this technology

  6. The IAEA's safeguards systems. Ready for the 21st century

    International Nuclear Information System (INIS)

    The publication reviews the IAEA's safeguards system, answering the following questions: What is being done to halt the further spread of nuclear weapons? Why are IAEA Safeguards important? what assurances do safeguards seek to provide? How are safeguards agreements implemented? What specific challenges have there been for IAEA verification? Can the IAEA prevent the diversion of declared Material? How has the safeguards system been strengthened? How much do safeguards cost? What is the future of IAEA verification? (author)

  7. 34 CFR 104.36 - Procedural safeguards.

    Science.gov (United States)

    2010-07-01

    ... Preschool, Elementary, and Secondary Education § 104.36 Procedural safeguards. A recipient that operates a... 34 Education 1 2010-07-01 2010-07-01 false Procedural safeguards. 104.36 Section 104.36 Education Regulations of the Offices of the Department of Education OFFICE FOR CIVIL RIGHTS, DEPARTMENT OF...

  8. Open source research and nuclear safeguards

    International Nuclear Information System (INIS)

    Full text: The paper will assess the utility of open source research for enhancing the collection and analysis of information related to nuclear safeguards. The International Centre for Security Analysis (ICSA) at King's College London adopts a cross-disciplinary approach for open source research relevant to nuclear safeguards by combining expertise in science and technology, political science, information technology and multiple languages including Arabic, Farsi, English, French, German, Japanese, Korean, Mandarin, Russian and Turkish. The paper will examine the following sets of issues related to open source research in the field of nuclear safeguards: - the various 'types' of open sources that are applicable to enhancing the analysis of nuclear safeguards issues (primary, secondary, technical and 'grey literature'); - the 'utility' of open source research in terms of enhancing the analysis of nuclear safeguards issues (contextual awareness, tip-off, response to unexpected contingencies); - the potential 'problems' associated with researching open sources related to nuclear safeguards issues (inaccuracy, bias, irrelevance, disinformation); - the 'challenges' involved in conducting open source research on nuclear safeguards issues (information overload, open versus closed societies. The paper will also highlight the challenges posed by open source analysis). The utility, problems and challenges associated with open source research in the field of nuclear safeguards will be illustrated with various thematic, regional and country-based examples. (author)

  9. Safeguards implications of laser isotope separation

    International Nuclear Information System (INIS)

    The purpose of this report is to describe and emphasise the safeguards and relevant features of atomic vapour laser isotope separation (AVLIS) and molecular laser isotope separation (MLIS), and to consider the issues that must be addressed before a safeguards approach at a commercial AVLIS or MLIS facility can be implemented. (Author)

  10. Structure for the decomposition of safeguards responsibilities

    International Nuclear Information System (INIS)

    A major mission of safeguards is to protect against the use of nuclear materials by adversaries to harm society. A hierarchical structure of safeguards responsibilities and activities to assist in this mission is defined. The structure begins with the definition of international or multi-national safeguards and continues through domestic, regional, and facility safeguards. The facility safeguards is decomposed into physical protection and material control responsibilities. In addition, in-transit safeguards systems are considered. An approach to the definition of performance measures for a set of Generic Adversary Action Sequence Segments (GAASS) is illustrated. These GAASS's begin outside facility boundaries and terminate at some adversary objective which could lead to eventual safeguards risks and societal harm. Societal harm is primarily the result of an adversary who is successful in the theft of special nuclear material or in the sabotage of vital systems which results in the release of material in situ. With the facility safeguards system, GAASS's are defined in terms of authorized and unauthorized adversary access to materials and components, acquisition of material, unauthorized removal of material, and the compromise of vital components. Each GAASS defines a set of ''paths'' (ordered set of physical protection components) and each component provides one or more physical protection ''functions'' (detection, assessment, communication, delay, neutralization). Functional performance is then developed based upon component design features, the environmental factors, and the adversary attributes. An example of this decomposition is presented

  11. IMPLEMENTING THE SAFEGUARDS-BY-DESIGN PROCESS

    Energy Technology Data Exchange (ETDEWEB)

    Whitaker, J Michael [ORNL; McGinnis, Brent [Oak Ridge National Laboratory (ORNL); Laughter, Mark D [ORNL; Morgan, Jim [Innovative Solutions; Bjornard, Trond [Idaho National Laboratory (INL); Bean, Robert [Idaho National Laboratory (INL); Durst, Phillip [Idaho National Laboratory (INL); Hockert, John [Pacific Northwest National Laboratory (PNNL); DeMuth, Scott [Los Alamos National Laboratory (LANL); Lockwood, Dunbar [U.S. Department of Energy, NNSA

    2010-01-01

    The Safeguards-by-Design (SBD) approach incorporates safeguards into the design and construction of nuclear facilities at the very beginning of the design process. It is a systematic and structured approach for fully integrating international and national safeguards for material control and accountability (MC&A), physical protection, and other proliferation barriers into the design and construction process for nuclear facilities. Implementing SBD is primarily a project management or project coordination challenge. This paper focuses specifically on the design process; the planning, definition, organization, coordination, scheduling and interaction of the safeguards experts and stakeholders as they participate in the design and construction of a nuclear facility. It delineates the steps in a nuclear facility design and construction project in order to provide the project context within which the safeguards design activities take place, describes the involvement of the safeguards experts in the design process, the nature of their analyses, interactions and decisions, and describes the documents created and how they are used. This report highlights the project context of safeguards activities, and identifies the safeguards community (nuclear facility operator, designer/builder, state regulator, SSAC and IAEA) must accomplish in order to implement SBD within the project.

  12. TASTEX: Tokai Advanced Safeguards Technology Exercise

    International Nuclear Information System (INIS)

    During the years 1978 to 1981 the Governments of France, Japan and the United States of America cooperated with the International Atomic Energy Agency in the TASTEX (Tokai Advanced Safeguards Technology Exercise) programme. The aim of this programme was to improve the technology for the application of international safeguards at reprocessing facilities, and the results are presented in the present report

  13. 7 CFR 947.55 - Safeguards.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 8 2010-01-01 2010-01-01 false Safeguards. 947.55 Section 947.55 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... safeguards to prevent shipments pursuant to § 947.54 from entering channels of trade and other outlets...

  14. NRC safeguards - An evolving policy

    International Nuclear Information System (INIS)

    The responsibilities of the Nuclear Regulatory Commission (NRC) related to the safeguarding of nuclear material derive from a number of legislative enactments which include the Energy Reorganization Act, The Nuclear Non-Proliferation Act and The Omnibus Diplomatic Security and Anti-Terrorism Act. The development of NRC material control and accounting requirements over the years has resulted in a number of refinements in system capabilities. A recent rule amendment will provide for more timely analysis of accounting data to enhance anomaly detection and resolution and thus provide for earlier detection of possible theft or diversion. This, along with present initiatives in physical protection program areas, combine to provide increase assurance in capabilities to adequately protect special nuclear materials. Among the physical protection measures now under consideration are revised requirements for security force training and the establishment of a formal requirement for tactical response exercises to evaluate security system effectiveness. In the international arena, full cooperation with the IAEA continues to be regarded as an important function. A recommendation in this area is to reconvene an international committee to review IAEA programs for physical protection (INFCIRC 225). NRC activities in support of these goals include the establishment of improving safeguards capabilities, requiring the reduction of enrichments used in nonpower reactor, the reduction of inventories of highly enriched uranium to levels actually needed for nonpower reactor operations, the maintenance of comparable levels of protection for weapons usable materials under Department of Energy and NRC programs, and continued support of IAEA initiatives and objectives

  15. Separations and safeguards model integration.

    Energy Technology Data Exchange (ETDEWEB)

    Cipiti, Benjamin B.; Zinaman, Owen

    2010-09-01

    Research and development of advanced reprocessing plant designs can greatly benefit from the development of a reprocessing plant model capable of transient solvent extraction chemistry. This type of model can be used to optimize the operations of a plant as well as the designs for safeguards, security, and safety. Previous work has integrated a transient solvent extraction simulation module, based on the Solvent Extraction Process Having Interaction Solutes (SEPHIS) code developed at Oak Ridge National Laboratory, with the Separations and Safeguards Performance Model (SSPM) developed at Sandia National Laboratory, as a first step toward creating a more versatile design and evaluation tool. The goal of this work was to strengthen the integration by linking more variables between the two codes. The results from this integrated model show expected operational performance through plant transients. Additionally, ORIGEN source term files were integrated into the SSPM to provide concentrations, radioactivity, neutron emission rate, and thermal power data for various spent fuels. This data was used to generate measurement blocks that can determine the radioactivity, neutron emission rate, or thermal power of any stream or vessel in the plant model. This work examined how the code could be expanded to integrate other separation steps and benchmark the results to other data. Recommendations for future work will be presented.

  16. Safeguards and retrievability from waste forms

    Energy Technology Data Exchange (ETDEWEB)

    Danker, W.

    1996-05-01

    This report describes issues discussed at a session from the PLutonium Stabilization and Immobilization Workshop related to safeguards and retrievability from waste forms. Throughout the discussion, the group probed the goals of disposition efforts, particularly an understanding of the {open_quotes}spent fuel standard{close_quotes}, since the disposition material form derives from these goals. The group felt strongly that not only the disposition goals but safeguards to meet these goals could affect the material form. Accordingly, the Department was encouraged to explore and apply safeguards as early in the implementation process as possible. It was emphasized that this was particularly true for any planned use of existing facilities. It is much easier to build safeguards approaches into the development of new facilities, than to backfit existing facilities. Accordingly, special safeguards challenges are likely to be encountered, given the cost and schedule advantages offered by use of existing facilities.

  17. Video image processing for nuclear safeguards

    International Nuclear Information System (INIS)

    The field of nuclear safeguards has received increasing amounts of public attention since the events of the Iraq-UN conflict over Kuwait, the dismantlement of the former Soviet Union, and more recently, the North Korean resistance to nuclear facility inspections by the International Atomic Energy Agency (IAEA). The role of nuclear safeguards in these and other events relating to the world's nuclear material inventory is to assure safekeeping of these materials and to verify the inventory and use of nuclear materials as reported by states that have signed the nuclear Nonproliferation Treaty throughout the world. Nuclear safeguards are measures prescribed by domestic and international regulatory bodies such as DOE, NRC, IAEA, and EURATOM and implemented by the nuclear facility or the regulatory body. These measures include destructive and non destructive analysis of product materials/process by-products for materials control and accountancy purposes, physical protection for domestic safeguards, and containment and surveillance for international safeguards

  18. International safeguards for reprocessing plants. Final report

    International Nuclear Information System (INIS)

    Proliferation risks inherent in reprocessing show the need to employ technically effective safeguards which can detect, with a high degree of assurance and on a timely basis, the diversion of significant quantities of fissionable material. A balance must be struck between what is technically feasible and effective and what is institutionally acceptable. Purpose of this report is to examine the several technical approaches to safeguards in light of their prospective acceptability. This study defines the economic, political and institutional nature of the safeguards problem; surveys generically alternative technical approaches to international safeguards including their effectiveness and relative development; characterizes the institutional implications and uncertainties associated with the acceptance and implementation of each technical alternative; and integrates these assessments into a set of overall judgments on feasible directions for reprocessing plant safeguards systems

  19. Microwave Filters

    OpenAIRE

    Zhou, Jiafeng

    2010-01-01

    The general theory of microwave filter design based on lumped-element circuit is described in this chapter. The lowpass prototype filters with Butterworth, Chebyshev and quasielliptic characteristics are synthesized, and the prototype filters are then transformed to bandpass filters by lowpass to bandpass frequency mapping. By using immitance inverters ( J - or K -inverters), the bandpass filters can be realized by the same type of resonators. One design example is given to verify the theory ...

  20. Safeguards Strategy in Physical Protection System for Nuclear Installation

    International Nuclear Information System (INIS)

    Safeguards strategy is directed at efforts of eliminating theft of nuclear materials and sabotage of nuclear installation. For achieving the above objective, it is necessary to set up safeguards strategy in physical protection of nuclear materials and installation. The safeguards strategy starts from anticipated security condition, list of thefts, planning referred to as safeguards planning. Safeguards planning are implemented in safeguards implementation, followed up then by evaluation. Results of evaluation are equipped with results of safeguards survey already developed. Safeguards' planning is made from these results and serve as guidelines for next safeguards implementation and is repeated to form a safeguard cycle. One safeguard cycle is made on a periodical basis, at least annually. (author)

  1. The spread of international safeguards

    International Nuclear Information System (INIS)

    The Treaty on the Non-Proliferation of Nuclear Weapons came into force on 5 March 1970 by the ratification of 40 non-nuclear-weapon States and that of three nuclear weapon States - the United Kingdom, the United States and the USSR. Since then it has been signed by 98 States, and now 73 States have ratified it. For more than a year the Safeguards Committee (1970), a Committee established by the Board and open to all member States of the Agency, discussed the Structure and Content of Agreements to be concluded between the Agency and States Party to the Treaty in order to fulfill their obligations under it. Today, of the 73 States that have ratified the NPT, agreements have already been concluded with 25 States, and negotiations are underway with 31 other States including the five non-nuclear-weapon States Members of the European Community (Euratom). At its June session, the Board of Governors of the IAEA approved the text of a co-operation agreement between the Agency and the Agency for the Prohibition of Nuclear Weapons in Latin America (OPANAL), which was established to ensure compliance with the obligations contracted by States Party to the Tlatelolco Treaty. It will be remembered that that Treaty was signed in Tlatelolco in 1967 by 22 Latin American countries. Since then 19 States have ratified it, and the additional protocols have been signed and ratified by two of the nuclear powers - the UK and the USA. As Dr. Eklund, Director General of the IAEA, has remarked, 'the Treaty of Tlatelolco could be regarded as the first multilateral treaty in the field of nuclear disarmament which provides for the application of an institutionalized and international control system, and as such it represented a decisive step forward in the recognition and acceptance of international safeguards'. Both the NPT and the Tlatelolco Treaty call upon the IAEA to perform one of its main statutory functions: that is, to apply safeguards at the request of the parties to a multilateral

  2. Water Filters

    Science.gov (United States)

    1993-01-01

    The Aquaspace H2OME Guardian Water Filter, available through Western Water International, Inc., reduces lead in water supplies. The filter is mounted on the faucet and the filter cartridge is placed in the "dead space" between sink and wall. This filter is one of several new filtration devices using the Aquaspace compound filter media, which combines company developed and NASA technology. Aquaspace filters are used in industrial, commercial, residential, and recreational environments as well as by developing nations where water is highly contaminated.

  3. Development and implementation of international safeguards

    International Nuclear Information System (INIS)

    The unique institution of International Atomic Energy Agency (IAEA) safeguards has been commented on at length by both technicians and politicians. IAEA safeguards have variously been extolled as a great international break-through and model for other arms control verification regimes and alternatively as a not very credible arrangement with many weaknesses and contradictions and which cannot, essentially by definition, do the job it's supposed to do. The 1981 bombing by Israel of the safeguarded Iraqi research reactor at Tuwaitha is used by both extremes to support their positions. As a physicist who has been working in this area, among others, for several years it seems to me that neither side is giving the reality of IAEA safeguards a fair deal. The bottom line on safeguards is to ensure that nuclear material, especially plutonium or highly enriched uranium (>20% U-236 but usually 93% U-235) under safeguards, is not used to make nuclear explosives or to further other military purposes. In the first instance they are pretty good and do represent a major concession by sovereign states; but the structure of the safeguards regime was designed in another era. The system has its flaws technically, but it is also a political system which, because of its dual nature can and does do a very useful and important job for the international community

  4. Remote monitoring for international safeguards

    International Nuclear Information System (INIS)

    Remote monitoring is not a new technology, and its application to safeguards relevant activities has been examined for a number of years. On behalf of the US Department of Energy and international partners, remote monitoring systems have been emplaced in nuclear facilities and laboratories in various parts of the world. The experience gained from these field trials of remote monitoring systems has shown the viability of the concept of using integrated monitoring systems. Although a wide variety of sensors has been used in the remote monitoring field trials conducted to date, the possible range of instrumentation that might be used has scarcely been touched. As the technology becomes widespread, large amounts of data will become available to inspectors responsible for safeguards activities at the sites. Effective use of remote monitoring will require processing, archiving, presenting, and assessing of these data. To provide reasonable efficiency in the application of this technology, data processing should be done in a careful and organized manner. The problem will be not an issue of poring over scant records but of surviving under a deluge of information made possible by modern technology. Fortunately, modern technology, which created the problem of the data glut, is available to come to the assistance of those inundated by data. Apart from the technological problems, one of the most important aspects of remote monitoring is the potential constraint related to the transmission of data out of a facility or beyond national borders. Remote monitoring across national borders can be seriously considered only in the context of a comprehensive, transparent, and open implementation regime

  5. Uncertainty Quantification for Safeguards Measurements

    International Nuclear Information System (INIS)

    Part of the scientific method requires all calculated and measured results to be accompanied by a description that meets user needs and provides an adequate statement of the confidence one can have in the results. The scientific art of generating quantitative uncertainty statements is closely related to the mathematical disciplines of applied statistics, sensitivity analysis, optimization, and inversion, but in the field of non-destructive assay, also often draws heavily on expert judgment based on experience. We call this process uncertainty quantification, (UQ). Philosophical approaches to UQ along with the formal tools available for UQ have advanced considerably over recent years and these advances, we feel, may be useful to include in the analysis of data gathered from safeguards instruments. This paper sets out what we hope to achieve during a three year US DOE NNSA research project recently launched to address the potential of advanced UQ to improve safeguards conclusions. By way of illustration we discuss measurement of uranium enrichment by the enrichment meter principle (also known as the infinite thickness technique), that relies on gamma counts near the 186 keV peak directly from 235U. This method has strong foundations in fundamental physics and so we have a basis for the choice of response model — although in some implementations, peak area extraction may result in a bias when applied over a wide dynamic range. It also allows us to describe a common but usually neglected aspect of applying a calibration curve, namely the error structure in the predictors. We illustrate this using a combination of measured data and simulation. (author)

  6. Safeguards and nuclear material accounting

    International Nuclear Information System (INIS)

    The safeguards activities performed under INFCIRC/153 type of agreements are often characterized as traditional safeguards. This approach contains three elements: nuclear material accountancy; containment and surveillance measures; and on-site inspections. The nuclear material accountancy establishes the quantity of nuclear material present and changes in that over a period of time. Containment and surveillance measures take advantage of physical boundaries like walls, containers, cameras and seals to restrict, control or monitor the movement of or access to nuclear material. On-site inspection verifies the credibility of the first two verification elements. When we consider accounting of nuclear material we must have in our mind a Material Balance Area (MBA) separated by a physical boundary. There should be a close accounting period and also a nuclear material to account for. If there is some beginning inventory (BPI) in the MBA, it might receipt some material say R from other source. Then after processing some end product say S has been transferred to other MBA. During the process some part of the material can not be used further so it has to be discarded after measurement. Let it be MD. At the end of period some part of the material is still left over in the MBA, call it EPI. Since the nuclear materials are of high monitory and strategic value. The objective of their accounting and control is the timely detection of diversion of significant quantities of nuclear material from peaceful nuclear activities - to the manufacture of nuclear weapons or of other nuclear explosive devices or for purposes unknown, and to deterrence of such diversion by the risk of early detection

  7. Goals of measurement systems for international safeguards

    International Nuclear Information System (INIS)

    The safeguards applied by the International Atomic Energy Agency are based on technical performance goals and criteria that have been developed, but not officially adopted by the Agency. The goals derive in part from the external consequences that safeguards are intended to prevent and in some cases on internal considerations of feasibility. To the extent that these goals may not be attainable, as may be the case with large-throughput bulk reprocessing plants, the Agency is placed in a difficult position. In this paper safeguards goals and criteria and their underlying rationales are critically examined. Suggestions for a more rational and workable structure of performance goals are offered

  8. IAEA Safeguards: Past, Present, and Future

    Energy Technology Data Exchange (ETDEWEB)

    Santi, Peter A. [Los Alamos National Laboratory; Hypes, Philip A. [Los Alamos National Laboratory

    2012-06-14

    This talk will present an overview of the International Atomic Energy Agency with a specific focus on its international safeguards mission and activities. The talk will first present a brief history of the IAEA and discuss its current governing structure. It will then focus on the Safeguards Department and its role in providing assurance that nuclear materials are being used for peaceful purposes. It will then look at how the IAEA is currently evolving the way in which it executes its safeguards mission with a focus on the idea of a state-level approach.

  9. Key Nuclear Verification Priorities - Safeguards and Beyond

    International Nuclear Information System (INIS)

    In addressing nuclear verification priorities, we should look beyond the current safeguards system. Non-proliferation, which the safeguards system underpins, is not an end in itself, but an essential condition for achieving and maintaining nuclear disarmament. Effective safeguards are essential for advancing disarmament, and safeguards issues, approaches and techniques are directly relevant to the development of future verification missions. The extent to which safeguards challenges are successfully addressed - or otherwise - will impact not only on confidence in the safeguards system, but on the effectiveness of, and confidence in, disarmament verification. To identify the key nuclear verification priorities, we need to consider the objectives of verification, and the challenges to achieving these. The strategic objective of IAEA safeguards might be expressed as: To support the global nuclear non-proliferation regime by: - Providing credible assurance that states are honouring their safeguards commitments - thereby removing a potential motivation to proliferate; and - Early detection of misuse of nuclear material and technology - thereby deterring proliferation by the risk of early detection, enabling timely intervention by the international community. Or to summarise - confidence-building, detection capability, and deterrence. These will also be essential objectives for future verification missions. The challenges to achieving these involve a mix of political, technical and institutional dimensions. Confidence is largely a political matter, reflecting the qualitative judgment of governments. Clearly assessments of detection capability and deterrence have a major impact on confidence. Detection capability is largely thought of as 'technical', but also involves issues of legal authority, as well as institutional issues. Deterrence has both political and institutional aspects - including judgments on risk of detection and risk of enforcement action being taken. The

  10. Development of DUPIC safeguards neutron counter

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Young Gil; Cha, Hong Ryul; Kim, Ho Dong; Hong, Jong Sook; Kang, Hee Young

    1999-08-01

    KAERI, in cooperation with LANL, developed DSNC (DUPIC Safeguards Neutron Counter) for safeguards implementing on DUPIC process which is under development by KAERI for direct use of spent PWR fuel in CANDU reactors. DSNC is a well-type neutron coincidence counter with substantial shielding to protect system from high gamma radiation of spent fuel. General development procedures in terms of design, manufacturing, fabrication, cold and hot test, performance test for DSNC authentication by KAERI-IAEA-LANL are described in this report. It is expected that the techniques related DSNC development and associated neutron detection and evaluation method could be applied for safeguards improvement. (Author). 20 refs., 16 tabs. 98 figs.

  11. Cosmokinetics: A joint analysis of Standard Candles, Rulers and Cosmic Clocks

    OpenAIRE

    Nair, Remya; Jhingan, Sanjay; Jain, Deepak

    2011-01-01

    We study the accelerated expansion of the universe by using the kinematic approach. In this context, we parameterize the deceleration parameter, q(z), in a model independent way. Assuming three simple parameterizations we reconstruct q(z). We do the joint analysis with combination of latest cosmological data consisting of standard candles (Supernovae Union2 sample), standard ruler (CMB/BAO), cosmic clocks (age of passively evolving galaxies) and Hubble (H(z)) data. Our results support the acc...

  12. The Candle and the Mirror: One Author's Journey as an Outsider.

    Science.gov (United States)

    Moreillon, Judi

    1999-01-01

    Chronicles the author's journey as an outsider who authored a book for children about the harvest traditions of the Tohono O'odham people. Describes how her concern about the lack of literature to serve as a mirror and a candle to reflect and illuminate the lives of Tohono O'odham children led her on a journey that was both painful and affirming.…

  13. The safeguards revolution: Contributions and perspectives of the Standing Advisory Group on Safeguards Implementation

    International Nuclear Information System (INIS)

    Full text: It is no exaggeration to describe the ongoing changes to the IAEA safeguards system as revolutionary. In the past decade safeguards have moved from a relatively routine system, operating in a seemingly benign environment, to a system undergoing radical change, having to reinvent itself to respond to major challenges. Yet the process of revolution has a long way to go. The conceptual framework for the new safeguards has been developed, but this framework has to be consolidated through new implementation practices. In this sense the revolution needs to be ongoing. There is much more to be done if the safeguards system is to be successful in meeting the challenges. When the traditional safeguards system was introduced, in the early 1970s following the conclusion of the NPT, the objectives of the safeguards system were seen as being very different to today. At that time it was thought that proliferation would require diversion of safeguarded nuclear material, and misuse of safeguarded nuclear facilities. It was considered beyond the capability of most States to establish a wholly clandestine nuclear fuel cycle, independent of safeguarded nuclear material and facilities. So, it was thought, countering proliferation was a matter of applying suitably rigorous safeguards procedures to declared material and facilities. During the 1970s and 1980s the traditional safeguards system developed in conditions of apparent stability, where the main challenge was seen as resource allocation, how to manage a steadily growing workload with a relatively static budget. During this period the traditional safeguards system developed with an emphasis on nuclear materials accountancy, and on verifying the correctness of declared nuclear material inventories. The organisational culture developed around the use of quantitative and relatively mechanistic procedures. This culture was reinforced through a particular policy perspective, specifically, that avoiding discrimination

  14. Histologic and Immunohistochemical Features of the Skin Lesions in CANDLE Syndrome.

    Science.gov (United States)

    Torrelo, Antonio; Colmenero, Isabel; Requena, Luis; Paller, Amy S; Ramot, Yuval; Richard Lee, Chyi-Chia; Vera, Angel; Zlotogorski, Abraham; Goldbach-Mansky, Raphaela; Kutzner, Heinz

    2015-07-01

    Chronic atypical neutrophilic dermatosis with lipodystrophy and elevated temperature (CANDLE) syndrome is a newly characterized autoinflammatory disorder, caused by mutations in PSMB8. It is characterized by early-onset fevers, accompanied by a widespread, violaceous, and often annular cutaneous eruption. Although the exact pathogenesis of this syndrome is still obscure, it is postulated that the inflammatory disease manifestations stem from excess secretion of interferons. Based on preliminary blood cytokine and gene expression studies, the signature seems to come mostly from type I interferons, which are proposed to lead to the recruitment of immature myeloid cells into the dermis and subcutis. In this study, we systematically analyzed skin biopsies from 6 patients with CANDLE syndrome by routine histopathology and immunohistochemistry methods. Skin lesions showed the presence of extensive mixed dermal and subcutaneous inflammatory infiltrate, composed of mononuclear cells, atypical myeloid cells, neutrophils, eosinophils, and some mature lymphocytes. Positive LEDER and myeloperoxidase staining supported the presence of myeloid cells. Positive CD68/PMG1 and CD163 staining confirmed the existence of histiocytes and monocytic macrophages in the inflammatory infiltrate. CD123 staining was positive, demonstrating the presence of plasmacytoid dendritic cells. Uncovering the unique histopathological and immunohistochemical features of CANDLE syndrome provides tools for rapid and specific diagnosis of this disorder and further insight into the pathogenesis of this severe life-threatening condition. PMID:26091509

  15. Status and future prospect of 48Ca double beta decay search in CANDLES

    Science.gov (United States)

    Iida, T.; Nakajima, K.; Ajimura, S.; Batpurev, T.; Chan, W. M.; Fushimi, K.; Hazama, R.; Kakubata, H.; Khai, B. T.; Kishimoto, T.; Li, X.; Maeda, T.; Masuda, A.; Matsuoka, K.; Morishita, K.; Nakatani, N.; Nomachi, M.; Noshiro, S.; Ogawa, I.; Ohata, T.; Osumi, H.; Suzuki, K.; Tamagawa, Y.; Tesuno, K.; Trang, V. T. T.; Uehara, T.; Umehara, S.; Yoshida, S.

    2016-05-01

    The observation of neutrino-less double beta decay (0vßß) would be the most practical way to prove the Majorana nature of the neutrino and lepton number violation. CANDLES studies 48Ca double beta decay using CaF2 scintillator. The main advantage of 48Ca is that it has the highest Q-value (4.27 MeV) among all the isotope candidates for 0vßß. The CANDLES III detector is currently operating with 300kg CaF2 crystals in the Kamioka underground observatory, Japan. In 2014, a detector cooling system and a magnetic cancellation coil was installed with the aim to increase light emission of CaF2 scintillator and photo-electron collection efficiency of the photo-multipliers. After this upgrade, light yield was increased to 1000 p.e./MeV which is 1.6 times larger than before. According to data analysis and simulation, main background source in CANDLES is turned out to be high energy external gamma-ray originating neutron capture on the surrounding materials, so called (n,γ). Upgrading the detector by installing neutron and gamma-ray shield can reduce the remaining main backgrounds by two order magnitude. In this report, we discuss the detail of (n,γ) and background reduction by additional shielding.

  16. Overview of the Facility Safeguardability Analysis (FSA) Process

    Energy Technology Data Exchange (ETDEWEB)

    Bari, Robert A.; Hockert, John; Wonder, Edward F.; Johnson, Scott J.; Wigeland, Roald; Zentner, Michael D.

    2012-08-01

    Executive Summary The safeguards system of the International Atomic Energy Agency (IAEA) is intended to provide the international community with credible assurance that a State is fulfilling its safeguards obligations. Effective and cost-efficient IAEA safeguards at the facility level are, and will remain, an important element of IAEA safeguards as those safeguards evolve towards a “State-Level approach.” The Safeguards by Design (SBD) concept can facilitate the implementation of these effective and cost-efficient facility-level safeguards (Bjornard, et al. 2009a, 2009b; IAEA, 1998; Wonder & Hockert, 2011). This report, sponsored by the National Nuclear Security Administration’s Office of Nuclear Safeguards and Security, introduces a methodology intended to ensure that the diverse approaches to Safeguards by Design can be effectively integrated and consistently used to cost effectively enhance the application of international safeguards.

  17. The development of a color-magnitude diagram for active galactic nuclei (AGN): hope for a new standard candle

    Science.gov (United States)

    McGinnis, G.; Chung, S.; Gonzales, E. V.; Gorjian, V.; Pruett, L.

    2015-12-01

    Of the galaxies in our universe, only a small percentage currently have Active Galactic Nuclei (AGN). These galaxies tend to be further out in the universe and older, and are different from inactive galaxies in that they emit high amounts of energy from their central black holes. These AGN can be classified as either Seyferts or quasars, depending on the amount of energy emitted from the center (less or more). We are studying the correlation between the ratio of dust emission and accretion disk emission to luminosities of AGN in order to determine if there is a relationship strong enough to act as a predictive model for distance within the universe. This relationship can be used as a standard candle if luminosity is found to determine distances in space. We have created a color-magnitude diagram depicting this relationship between luminosity and wavelengths, similar to the Hertzsprung-Russell (HR) diagram. The more luminous the AGN, the more dust surface area over which to emit energy, which results in a greater near-infrared (NIR) luminosity. This differs from previous research because we use NIR to differentiate accretion from dust emission. Using data from the Sloan Digital Sky Survey (SDSS) and the Two Micron All Sky Survey (2MASS), we analyzed over one thousand Type 1 Seyferts and quasars. We studied data at different wavelengths in order to show the relationship between color (the ratio of one wavelength to another) and luminosity. It was found that plotting filters i-K (the visible and mid-infrared regions of the electromagnetic spectrum) against the magnitude absolute K (luminosity) showed a strong correlation. Furthermore, the redshift range between 0.14 and 0.15 was the most promising, with an R2 of 0.66.

  18. Safeguards research at Lawrence Livermore Laboratory

    International Nuclear Information System (INIS)

    The LLL safeguards research program includes inspection methods, facility assessment methodologies, value-impact analysis, vulnerability analysis of accounting systems, compliance with regulations, process monitoring, etc. Each of those projects is described as are their goals and progress

  19. 7 CFR 987.59 - Safeguards.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 8 2010-01-01 2010-01-01 false Safeguards. 987.59 Section 987.59 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... objectives of this part. Reports and Records...

  20. Safeguards Workforce Repatriation, Retention and Utilization

    Energy Technology Data Exchange (ETDEWEB)

    Gallucci, Nicholas [Brookhaven National Lab. (BNL), Upton, NY (United States); Poe, Sarah [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2015-10-01

    Brookhaven National Laboratory was tasked by NA-241 to assess the transition of former IAEA employees back to the United States, investigating the rate of retention and overall smoothness of the repatriation process among returning safeguards professionals. Upon conducting several phone interviews, study authors found that the repatriation process went smoothly for the vast majority and that workforce retention was high. However, several respondents expressed irritation over the minimal extent to which their safeguards expertise had been leveraged in their current positions. This sentiment was pervasive enough to prompt a follow-on study focusing on questions relating to the utilization rather than the retention of safeguards professionals. A second, web-based survey was conducted, soliciting responses from a larger sample pool. Results suggest that the safeguards workforce may be oversaturated, and that young professionals returning to the United States from Agency positions may soon encounter difficulties finding jobs in the field.

  1. A historical review of international safeguards

    International Nuclear Information System (INIS)

    Beginning from the 'Three Nations Agreed Declaration' of November 1945 (US, UK, Canada) up to the ratification of the NPT and the acceptance of the IAEA safeguards and control by the member states. (HP)

  2. The Concept of Goals-Driven Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    R. Wigeland; T Bjornard; B. Castle

    2009-02-01

    The IAEA, NRC, and DOE regulations and requirements for safeguarding nuclear material and facilities have been reviewed and each organization’s purpose, objectives, and scope are discussed in this report. Current safeguards approaches are re-examined considering technological advancements and how these developments are changing safeguards approaches used by these organizations. Additionally, the physical protection approaches required by the IAEA, NRC, and DOE were reviewed and the respective goals, objectives, and requirements are identified and summarized in this report. From these, a brief comparison is presented showing the high-level similarities among these regulatory organizations’ approaches to physical protection. The regulatory documents used in this paper have been assembled into a convenient reference library called the Nuclear Safeguards and Security Reference Library. The index of that library is included in this report, and DVDs containing the full library are available.

  3. Potential nuclear safeguards applications for neutron generators

    International Nuclear Information System (INIS)

    Many nuclear safeguards inspection instruments use neutron sources to interrogate the fissile material (commonly 235U and 239Pu) to be measured. The neutron sources currently used in these instruments are isotopics such as Californium-252, Americium-Lithium, etc. It is becoming increasingly more difficult to transport isotopic sources from one measurement location to another. This represents a significant problem for the International Atomic Energy Agency (IAEA) safeguards inspectors because they must take their safeguards instruments with them to each nuclear installation to make an independent measurement. Purpose of this paper is to review the possibility of replacing isotopic neutron sources now used in IAEA safeguards instruments with electric neutron sources such as deuterium-tritium (D-T, 14-MeV neutrons) or deuterium-deuterium (D-D, 2-MeV neutrons). The potential for neutron generators to interrogate spent-light water reactor fuel assemblies in storage pools is also reviewed

  4. Advanced safeguards for the nuclear renaissance

    Energy Technology Data Exchange (ETDEWEB)

    Miller, Michael C [Los Alamos National Laboratory; Menlove, Howard O [Los Alamos National Laboratory

    2008-01-01

    The global expansion of nuclear energy provides not only the benefit of carbon-neutral electricity, but also the potential for proliferation concern as well. Nuclear safeguards implemented at the state level (domestic) and at the international level by the International Atomic Energy Agency (IAEA) are essential for ensuring that nuclear materials are not misused and are thereby a critical component of the increased usage of nuclear energy. In the same way that the 1950's Atoms for Peace initiative provided the foundation for a robust research and development program in nuclear safeguards, the expansion of nuclear energy that is underway today provides the impetus to enter a new era of technical development in the safeguards community. In this paper, we will review the history of nuclear safeguards research and development as well future directions.

  5. Optimal filtering

    CERN Document Server

    Anderson, Brian D O

    2005-01-01

    This graduate-level text augments and extends beyond undergraduate studies of signal processing, particularly in regard to communication systems and digital filtering theory. Vital for students in the fields of control and communications, its contents are also relevant to students in such diverse areas as statistics, economics, bioengineering, and operations research.Topics include filtering, linear systems, and estimation; the discrete-time Kalman filter; time-invariant filters; properties of Kalman filters; computational aspects; and smoothing of discrete-time signals. Additional subjects e

  6. The Department of Safeguards Quality Management System

    International Nuclear Information System (INIS)

    The International Atomic Energy Agency (IAEA) Department of Safeguards quality management system (QMS) provides the framework for all activities that support the Agency's commitment to providing soundly-based safeguards conclusions regarding the peaceful use of nuclear material. The focus of the QMS is to enhance the effectiveness and efficiency of safeguards implementation through defined, documented processes, routine oversight and continual improvement initiatives. In accordance with QMS principles, the high-level business processes representing the Department's activities are defined in procedures, guidelines and policies that are maintained in the Safeguards Document Manager. These processes form the basis for Department operations for drawing safeguards conclusions regarding State's compliance with their safeguards obligations. Oversight is provided through internal quality audits. These audits are targeted at processes selected by Senior Management with a focus on procedure compliance as well as customer expectations. Best practices and areas for improvement are assessed through continual improvement. Noncompliance and conditions that are adverse to quality are identified and analyzed in the Condition Report System. Root cause analysis and the implementation actions to eliminate the cause reduce the chance of condition recurrence. Through continual process improvement, processes are measured and analyzed to reduce process and administration waste. The improved processes improve efficiency while providing the desired results. Within the scope of the QMS, these tools support the performance of Departmental processes so that Safeguards products achieve the intended purpose. This paper describes how the various elements of the Department's QMS support safeguards implementation. (author)

  7. IAEA safeguards instrumentation: Development, implementation and control

    International Nuclear Information System (INIS)

    Extensive development efforts over the last 5 years have produced a number of new instruments to help the IAEA meet its safeguards obligations. Implementation of these new instruments is proceeding at a necessarily slower pace. To optimize the performance and reliability of the instrumentation systems when used in safeguards applications, increasing attention is needed to be spent on performance monitoring and control of the instruments. (author)

  8. Measurement trends for future safeguards systems

    International Nuclear Information System (INIS)

    Safeguards for future commercial-scale nuclear facilities may employ three materials control and accounting concepts: classical accounting, dynamic materials balancing, and independent verification of inventories and materials balances. Typical measurement needs associated with the implementation of these concepts at high-throughput facilities are discussed. Promising measurement methods for meeting these needs are described and recent experience is cited. General directions and considerations for meeting advanced safeguards systems needs through measurement technology development over the next decade are presented

  9. Next Generation Safeguards Initiative: Human Capital Development

    International Nuclear Information System (INIS)

    Since 2008, the Human Capital Development (HCD) subprogramme of the U.S. National Nuclear Security Administration's (NNSA) Next Generation Safeguards Initiative (NGSI) has supported the recruitment, education, training, and retention of the next generation of international safeguards professionals to meet the needs of both the International Atomic Energy Agency (IAEA) and the United States. Specifically, HCD's efforts respond to data indicating that 82% of safeguards experts at U.S. Laboratories will have left the workforce within 15 years. This paper provides an update on the status of the subprogramme since its last presentation at the IAEA Safeguards Symposium in 2010. It highlights strengthened, integrated efforts in the areas of graduate and post-doctoral fellowships, young and midcareer professional support, short safeguards courses, and university engagement. It also discusses lessons learned from the U.S. experience in safeguards education and training as well as the importance of long-range strategies to develop a cohesive, effective, and efficient human capital development approach. (author)

  10. Advanced Safeguards Approaches for New Reprocessing Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Durst, Philip C.; Therios, Ike; Bean, Robert; Dougan, A.; Boyer, Brian; Wallace, Richard; Ehinger, Michael H.; Kovacic, Don N.; Tolk, K.

    2007-06-24

    U.S. efforts to promote the international expansion of nuclear energy through the Global Nuclear Energy Partnership (GNEP) will result in a dramatic expansion of nuclear fuel cycle facilities in the United States. New demonstration facilities, such as the Advanced Fuel Cycle Facility (AFCF), the Advanced Burner Reactor (ABR), and the Consolidated Fuel Treatment Center (CFTC) will use advanced nuclear and chemical process technologies that must incorporate increased proliferation resistance to enhance nuclear safeguards. The ASA-100 Project, “Advanced Safeguards Approaches for New Nuclear Fuel Cycle Facilities,” commissioned by the NA-243 Office of NNSA, has been tasked with reviewing and developing advanced safeguards approaches for these demonstration facilities. Because one goal of GNEP is developing and sharing proliferation-resistant nuclear technology and services with partner nations, the safeguards approaches considered are consistent with international safeguards as currently implemented by the International Atomic Energy Agency (IAEA). This first report reviews possible safeguards approaches for the new fuel reprocessing processes to be deployed at the AFCF and CFTC facilities. Similar analyses addressing the ABR and transuranic (TRU) fuel fabrication lines at AFCF and CFTC will be presented in subsequent reports.

  11. FUTURE SAFEGUARDS EFFECTIVENESS: CONCEPTS AND ISSUES

    Energy Technology Data Exchange (ETDEWEB)

    K. W. BUDLONG-SYLVESTER; J. F. PILAT

    2000-09-01

    With new safeguards measures (under old and new authority) now available to the International Atomic Energy Agency (IAEA), there will be fundamental changes in the manner IAEA safeguards are implemented, raising questions about their effectiveness in meeting expanded Agency safeguards objectives. In order to characterize the capability of various safeguards approaches in meeting their objectives, it will be necessary to fully understand what is involved in the new safeguards equation. Both old and new measures will be required to construct a comprehensive picture of a State's nuclear activities and capabilities, and they both have strengths and weaknesses. There are (for political and cost reasons) likely to be tradeoffs between the two types of measures. Significant differences among measures with respect to the probability of their detecting an anomaly, along with other characteristics, need be considered in this context. Given the important role of both types of measures in future approaches, their inherent differences with regard to their capabilities and limitations, and their potential impact on the credibility of safeguards, it will be essential to consider these measures systematically, independently, and in combination in any effectiveness evaluation. This paper will consider concepts and issues in addressing this need.

  12. Integrating virtual reality applications in nuclear safeguards

    International Nuclear Information System (INIS)

    Virtual reality (VR) tools have already been developed and deployed in the nuclear industry, including in nuclear power plant construction, project management, equipment and system design, and training. Recognized as powerful tools for, inter alia, integration of data, simulation of activities, design of facilities, validation of concepts and mission planning, their application in nuclear safeguards is still very limited. However, VR tools may eventually offer transformative potential for evolving the future safeguards system to be more fully information-driven. The paper focuses especially on applications in the area of training that have been underway in the Department of Safeguards of the International Atomic Energy Agency. It also outlines future applications envisioned for safeguards information and knowledge management, and information-analytic collaboration. The paper identifies some technical and programmatic pre-requisites for realizing the integrative potential of VR technologies. If developed with an orientation to integrating applications through compatible platforms, software, and models, virtual reality tools offer the long-term potential of becoming a real 'game changer,' enabling a qualitative leap in the efficiency and effectiveness of nuclear safeguards. The IAEA invites Member States, industry, and academia to make proposals as to how such integrating potential in the use of virtual reality technology for nuclear safeguards could be realized. (author)

  13. International and regional safeguards inspector training guidelines

    International Nuclear Information System (INIS)

    Recent international developments have prompted a need to strengthen the nuclear non-proliferation regime, the supporting international safeguards system, and related new inspection requirements. The U.S. Department of Energy (DOE) in carrying out its responsibilities for international safeguards, and in coordination with other U.S. agencies and the International Atomic Energy Agency (IAEA), initiated a study to identify training programs, techniques, and technologies that might enhance implementation of international nuclear safeguards inspections. As a result, an analysis of training needs was conducted and a set of guidelines was developed to assist in meeting future international safeguards inspection requirements. The objectives of the analysis and guidelines were to (1) to identify the knowledge, skills, and abilities required for international safeguards inspections with emphasis of new requirements; (2) identify training needs and resources available; and (3) sharpen the sense and understanding of the inspector's role. This paper summarizes the findings of this study and discusses potential applications of new training technologies to safeguards inspectors' needs

  14. Safeguards culture on 3S interfaces

    International Nuclear Information System (INIS)

    But when proliferation of nuclear weapon does happen due to violation of safeguards, the impact would be no smaller compare to the others. Therefore, it should be treated as important as the others. In fact, safeguards culture wasn't issued first time in this paper. However, the past safeguards culture only meant the conception based upon specific purpose. But it should be generalized to extend the target and scope enough to cover any possible misbehavior. The aforementioned NMAC will be a quite meaningful research subject not just for strengthening safeguards culture, but also for the security and safeguards interface. Recognizing the importance of this, the , IAEA has developed a set of technical criteria based on the IAEA implementing guide entitled Use of Nuclear Material Accounting and Control for Nuclear Security Purposes at Facilities(in publication) and a methodology to assess the use of a facility's NMAC system for nuclear security. IAEA has established an expert team to continuously evaluate and apply NMAC systems going forward. In the process of such efforts, the ROK should work to select and apply appropriate features so as to build a more improved safeguards culture and to determine the best practice

  15. Safeguards culture on 3S interfaces

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Yon Hong; Lee, Na Young; Han, Jae-Jun [Korea Institute of Nuclear Non-proliferation and Control, Daejeon (Korea, Republic of)

    2015-05-15

    But when proliferation of nuclear weapon does happen due to violation of safeguards, the impact would be no smaller compare to the others. Therefore, it should be treated as important as the others. In fact, safeguards culture wasn't issued first time in this paper. However, the past safeguards culture only meant the conception based upon specific purpose. But it should be generalized to extend the target and scope enough to cover any possible misbehavior. The aforementioned NMAC will be a quite meaningful research subject not just for strengthening safeguards culture, but also for the security and safeguards interface. Recognizing the importance of this, the , IAEA has developed a set of technical criteria based on the IAEA implementing guide entitled Use of Nuclear Material Accounting and Control for Nuclear Security Purposes at Facilities(in publication) and a methodology to assess the use of a facility's NMAC system for nuclear security. IAEA has established an expert team to continuously evaluate and apply NMAC systems going forward. In the process of such efforts, the ROK should work to select and apply appropriate features so as to build a more improved safeguards culture and to determine the best practice.

  16. Development of national safeguards inspection technology

    International Nuclear Information System (INIS)

    It is considered that the safeguards trend in the IAEA and international nonproliferation regime is being accelerated toward strengthened safeguards system. In order to effectively respond to the stream as a whole, government has to have a firm policy-intention on nuclear non-proliferation, and supporting stance as to the stream should be taken consistently. Also, technological development satisfying the non-proliferation requirement would be pursued for the establishment of transparency and the enhancement of international confidence. At present, Korea stands at take-off stage in terms of safeguards. Therefore, necessary measures such as arrangement of legal framework, staffing and training of inspection man-power, and purchase of inspection equipment should be taken at the same time for earlier settlement of national safeguards system. In this connection, international cooperation with the share of the inspection results and equipment between the IAEA and TCNC is demanded. In the long term, the development of inspection technology as well as the research of sophisticated technology will have to be pursued. Emphasis should be placed on the regional safeguards system as well. In addition, it is necessary to ensure internationally that nuclear technological development to be planned is development of safeguards technology. (author). 20 tabs., 24 figs., 45 refs

  17. AFCI Safeguards Enhancement Study: Technology Development Roadmap

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Leon E.; Dougan, A.; Tobin, Stephen; Cipiti, B.; Ehinger, Michael H.; Bakel, A. J.; Bean, Robert; Grate, Jay W.; Santi, P.; Bryan, Steven; Kinlaw, M. T.; Schwantes, Jon M.; Burr, Tom; Lehn, Scott A.; Tolk, K.; Chichester, David; Menlove, H.; Vo, D.; Duckworth, Douglas C.; Merkle, P.; Wang, T. F.; Duran, F.; Nakae, L.; Warren, Glen A.; Friedrich, S.; Rabin, M.

    2008-12-31

    The Advanced Fuel Cycle Initiative (AFCI) Safeguards Campaign aims to develop safeguards technologies and processes that will significantly reduce the risk of proliferation in the U.S. nuclear fuel cycle of tomorrow. The Safeguards Enhancement Study was chartered with identifying promising research and development (R&D) directions over timescales both near-term and long-term, and under safeguards oversight both domestic and international. This technology development roadmap documents recognized gaps and needs in the safeguarding of nuclear fuel cycles, and outlines corresponding performance targets for each of those needs. Drawing on the collective expertise of technologists and user-representatives, a list of over 30 technologies that have the potential to meet those needs was developed, along with brief summaries of each candidate technology. Each summary describes the potential impact of that technology, key research questions to be addressed, and prospective development milestones that could lead to a definitive viability or performance assessment. Important programmatic linkages between U.S. agencies and offices are also described, reflecting the emergence of several safeguards R&D programs in the U.S. and the reinvigoration of nuclear fuel cycles across the globe.

  18. Next Generation Safeguards Initiative Workshop on Enhanced Recruiting for International Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Pepper,S.; Rosenthal, M.; Fishbone, L.; Occhiogrosso, D.; Carroll, C.; Dreicer, M.; Wallace, R.; Rankhauser, J.

    2008-10-22

    In 2007, the National Nuclear Security Administration's Office of Nonproliferation and International Security (NA-24) completed a yearlong review of the challenges facing the international safeguards system today and over the next 25 years. The study found that without new investment in international safeguards, the U.S. safeguards technology base, and our ability to support International Atomic Energy Agency (IAEA) safeguards, will continue to erode and soon may be at risk. To reverse this trend, the then U.S. Secretary of Energy, Samuel Bodman, announced at the 2007 IAEA General Conference that the Department of Energy (DOE) would launch the Next Generation Safeguards Initiative (NGSI). He stated 'IAEA safeguards must be robust and capable of addressing proliferation threats. Full confidence in IAEA safeguards is essential for nuclear power to grow safely and securely. To this end, the U.S. Department of Energy will seek to ensure that modern technology, the best scientific expertise, and adequate resources are available to keep pace with expanding IAEA responsibilities.' To meet this goal, the NGSI objectives include the recruitment of international safeguards experts to work at the U.S. national laboratories and to serve at the IAEA's headquarters. Part of the latter effort will involve enhancing our existing efforts to place well-qualified Americans in a sufficient number of key safeguards positions within the IAEA's Department of Safeguards. Accordingly, the International Safeguards Project Office (ISPO) at Brookhaven National Laboratory (BNL) hosted a Workshop on Enhanced Recruiting for International Safeguards (ERIS) on October 22 and 23, 2008. The ISPO used a workshop format developed earlier with Sonalysts, Inc., that was followed at the U.S. Support Program's (USSP's) technology road-mapping sessions. ISPO invited participants from the U.S. DOE, the IAEA, the U.S. national laboratories, private industry, academia, and

  19. Safeguards Implementation Practices Guide on Establishing and Maintaining State Safeguards Infrastructure

    International Nuclear Information System (INIS)

    The IAEA implements safeguards pursuant to agreements concluded with States. It is in the interests of both States and the IAEA to cooperate to facilitate the practical implementation of safeguards. Such cooperation is explicitly required under all types of safeguards agreements. Effective cooperation depends upon States and the IAEA sharing a common understanding of their respective rights and obligations. To address this, in 2012 the IAEA published Services Series 21, Guidance for States Implementing Comprehensive Safeguards Agreements and Additional Protocols, which aimed at enhancing understanding of the safeguards obligations of both States and the IAEA and at improving their cooperation in safeguards implementation. States may establish different processes and procedures at the national level, and set up different systems as required to meet their safeguards obligations. Indeed, a variety of approaches are to be expected, owing to such differences as the size and complexity of States’ nuclear programmes and their regulatory framework. The purpose of this Safeguards Implementation Practices (SIP) Guide is to share the experiences and good practices as well as the lessons learned by both States and the IAEA, acquired over the many decades of safeguards implementation. The information contained in the SIP Guides is provided for explanatory purposes and use of the Guides is not mandatory. The descriptions in the SIP Guides have no legal status and are not intended to add to, subtract from, amend or derogate from, in any way, the rights and obligations of the IAEA and the States set forth in The Structure and Content of Agreements between the Agency and States Required in Connection with the Treaty on the Non-Proliferation of Nuclear Weapons (issued as INFCIRC/153 (Corrected)) and Model Protocol Additional to the Agreement(s) between State(s) and the International Atomic Energy Agency for the Application of Safeguards (issued as INFCIRC/540 (Corrected)). This

  20. Designing Data Protection Safeguards Ethically

    Directory of Open Access Journals (Sweden)

    Ugo Pagallo

    2011-03-01

    Full Text Available Since the mid 1990s, lawmakers and scholars have worked on the idea of embedding data protection safeguards in information and communication technology (ICT with the aim to access and control personal data in compliance with current regulatory frameworks. This effort has been strengthened by the capacities of computers to draw upon the tools of artificial intelligence (AI and operations research. However, work on AI and the law entails crucial ethical issues concerning both values and modalities of design. On one hand, design choices might result in conflicts of values and, vice versa, values may affect design features. On the other hand, the modalities of design cannot only limit the impact of harm-generating behavior but also prevent such behavior from occurring via self-enforcement technologies. In order to address some of the most relevant issues of data protection today, the paper suggests we adopt a stricter, yet more effective version of “privacy by design.” The goal should be to reinforce people’s pre-existing autonomy, rather than having to build it from scratch.

  1. Safeguards Envelope: The First Steps

    Energy Technology Data Exchange (ETDEWEB)

    Richard Metcalf; Jean Ragusa; Robert Bean

    2008-03-01

    The possibility exists for real time accountancy and assay of nuclear materials as they move through a reprocessing facility. This project aims to establish working parameters and local figures of merit to identify possible diversion in real time with minimal operational impact. Factors such as pH, NOX gas concentration, flow speeds and radiation fields are rarely taken into account in safeguards methodologies and will be included to increase the confidence of location and assay of nuclear materials. An adaptable, real data model is being created of the contactors of the Advanced Fuel Cycle Facility and will be analyzed using the appropriate modeling codes. This model will then be subjected to three, diversion scenarios and a figure of merit methodology will be utilized to create the operational parameters under which these diversion scenarios would be detected. This analysis for figure of merit methodology will include statistical fluctuations, operator error, and a rudimentary analysis of transient conditions. The long term goal of the project includes expansion universally over the plant, methods of detection without requiring access to proprietary information, and an evaluation of the requirements for future figure of merit methodologies.

  2. THE CANDLE FLAMES IN MICROGRAVIT%微重力环境中的蜡烛火焰

    Institute of Scientific and Technical Information of China (English)

    杜文锋; 张孝谦; 韦明罡; 华泳; 孔文俊

    2000-01-01

    对蜡烛火焰动态特征的分析表明,从正常重力状态过渡到微重力状态,火焰的空气动力学特征比质量和能量的传输特征的变化快。通过一台差分干涉仪首次测量得到了微重力环境中蜡烛火焰的温度。结果表明,微重力蜡烛火焰的温度小于正常重力蜡烛火焰的温度。微重力蜡烛火焰之所以呈蓝色是因为其温度小于烟黑生成的阈值温度1300 K。但当环境氧浓度足够高时,火焰温度大于烟黑生成的阈值温度,火焰中明显有烟黑生成,颜色为亮黄色。%The analysis of transient process of candle flame from normal gravity to microgravity shows that the variation of the aerodynamic feature is much faster than that of transport feature. The candle flame temperature was measured by the use of an interferometer in microgravity. The results show that candle flame temperature in microgravity is indeed lower than that in normal gravity.It is the reason for the candle flame is dim blue that the candle flame temperature is lower than 1300 K, the threshold temperature of soot formation.If The candle flame temperature in microgravity at 21%O2/79%N2 concentration is lower than the threshold temperature of soot formation of 1300K. That is the reason why the candle flame is dim blue at microgravity. However, if the ambient oxygen concentration is high enough, the candle flame temperature will be higher than the threshold temperature, so that soot will produce, and the color of candle flame will be bright yellow all the time even in microgravity.

  3. Secure data communication for safeguards implementation

    International Nuclear Information System (INIS)

    Secure, reliable and cost-effective communication is necessary for effective IAEA safeguards implementation. The transmission of safeguards data from nuclear facilities to IAEA headquarters and regional offices (referred to as remote monitoring) initially demonstrated the need for secure, cost-effective data communication that satisfies the confidentiality requirements of Member States and provides data authenticity that allows the IAEA to draw soundly based, independent safeguards conclusions. The implementation of integrated safeguards further demonstrates the need for information obtained in the course of an inspection, complementary access or design information verification, to be analyzed and corroborated with other information available at IAEA headquarters or regional offices while the inspector is still on-site. This requires the capability to connect the inspector, anywhere in the field, to the IAEA data network with secure voice, video, or data transfer capabilities. Such a data network would allow inspectors to 'push' information to headquarters, thereby providing IAEA managers with the ability to make evaluation in near real time, as well as the ability to 'pull' information from IAEA databases for evaluations in the field. In order to expand the IAEA's present capabilities in the area of secure data communication, in 2005 the Safeguards Division of Technical Support (SGTS) initiated cooperation with the European Space Agency (ESA) on satellite communications. This cooperation included testing an ESA provided satellite terminal at IAEA headquarters and at a nuclear facility. Two feasibility studies were carried out to address end-to-end communication services based on existing orbital and ground-based infrastructures. The goal was to determine how the deployment of advanced satellite communication and services could meet future IAEA safeguards needs. The paper presents the results of these studies, including a summary of costs, benefits and possible

  4. Building a Successful Machine Safeguarding Program

    Energy Technology Data Exchange (ETDEWEB)

    McConnell, S

    2003-03-06

    Safeguarding hazards associated with machines is a goal common to all health and safety professionals. Whether the individual is new to the safety field or has held associated responsibilities for a period of time, safeguarding personnel who work with or around machine tools and equipment should be considered an important aspect of the job. Although significant progress has been made in terms of safeguarding machines since the era prior to the organized safety movement, companies continue to be cited by the Occupational Safety and Health Administration (OSHA) and workers continue to be injured, even killed by machine tools and equipment. In the early 1900s, it was common practice to operate transmission machinery (gears, belts, pulleys, shafting, etc.) completely unguarded. At that time, the countersunk set screw used on shafting had not been invented and projecting set screws were involved in many horrific accidents. Manufacturers built machines with little regard for worker safety. Workers were killed or seriously injured before definitive actions were taken to improve safety in the workplace. Many states adopted legislation aimed at requiring machine guarding and improved injury reduction. The first patent for a machine safeguard was issued in 1868 for a mechanical interlock. Other patents followed. As methods for safeguarding machinery and tools were developed, standards were written and programs were set up to monitor factories for compliance. Many of those standards continue to govern how we protect workers today. It is common to see machine tools built in the forties, fifties and sixties being used in machine shops today. In terms of safeguarding, these machines may be considered poorly designed, improperly safeguarded or simply unguarded. In addition to the potential threat of an OSHA citation, these conditions expose the operator to serious hazards that must be addressed. The safety professional can help line management determine workable solutions for

  5. Next Generation Safeguards Initiative Workshop on Enhanced Recruiting for International Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Pepper,S.E.; Rosenthal, M.D.; Fishbone, L.G.; Occhogrosso, D.M.; Lockwood, D.; Carroll, C.J.; Dreicer, M.; Wallace, R.; Fankhauser, J.

    2009-07-12

    Brookhaven National Laboratory (BNL) hosted a Workshop on Enhanced Recruiting for International Safeguards October 22 and 23, 2008. The workshop was sponsored by DOE/NA-243 under the Next Generation Safeguards Initiative (NGSI). Placing well-qualified Americans in sufficient number and in key safeguards positions within the International Atomic Energy Agency’s (IAEA’s) Department of Safeguards is an important U.S. non-proliferation objective. The goal of the NGSI Workshop on Enhanced Recruiting for International Safeguards was to improve U.S. efforts to recruit U.S. citizens for IAEA positions in the Department of Safeguards. The participants considered the specific challenges of recruiting professional staff, safeguards inspectors, and managers. BNL’s International Safeguards Project Office invited participants from the U.S. Department of Energy, the IAEA, U.S. national laboratories, private industry, academia, and professional societies who are either experts in international safeguards or who understand the challenges of recruiting for technical positions. A final report for the workshop will be finalized and distributed in early 2009. The main finding of the workshop was the need for an integrated recruitment plan to take into account pools of potential candidates, various government and private agency stakeholders, the needs of the IAEA, and the NGSI human capital development plan. There were numerous findings related to and recommendations for maximizing the placement of U.S. experts in IAEA Safeguards positions. The workshop participants offered many ideas for increasing the pool of candidates and increasing the placement rate. This paper will provide details on these findings and recommendations

  6. Hot-Gas Filter Ash Characterization Project

    Energy Technology Data Exchange (ETDEWEB)

    Dockter, B.A.; Hurley, J.P.; Watne, T.A.; Katrinak, K.A.; O`Keefe, C.A. [North Dakota Univ., Grand Forks, ND (United States). Energy and Minerals Research Center

    1996-12-31

    Large-scale hot-gas testing over the past several years has revealed numerous cases of cake buildup on filter elements that have been difficult, if not impossible to remove. At times, the cake can bridge between candle filters, leading to high filter failure rates. Physical factors, including particle-size distribution, particle shape, the aerodynamics of deposition, and system temperature contribute to difficulty in removing the cake. It is speculated that chemical as well as physical effects are playing a role in leading the ash to bond to the filter or to itself. The Energy and Environmental research Center (EERC) at the University of North Dakota is working with Electric Power Research Institute (EPRI) and a consortium of companies in partnership with the US Department of Energy (DOE) to perform the research necessary to determine the factors that cause hot-gas cleanup filters to be blinded by ash or to develop deposits that can bridge the filters and cause them to fail. The objectives of this overall project are threefold: first, to determine the mechanisms by which difficult-to-clean ash is formed; second, to develop a method to determine the rate of blinding/bridging based on fuel and sorbent properties and operating conditions; finally, to provide suggestions fro ways to prevent filter blinding by the troublesome ash. The projects consists of four tasks: field sampling and archive sample analyses, laboratory-scale testing, bench-scale testing, and model and database development testing. This paper present preliminary data from Task 2 on determining the tensile strengths of coal ash particles at elevated temperatures and simulated combustor gas conditions.

  7. The state-level approach: moving beyond integrated safeguards

    International Nuclear Information System (INIS)

    The concept of a State-Level Approach (SLA) for international safeguards planning, implementation, and evaluation was contained in the Conceptual Framework for Integrated Safeguards (IS) agreed in 2002. This paper describes briefly the key elements of the SLA, including State-level factors and high-level safeguards objectives, and considers different cases in which application of the SLA methodology could address safeguards for 'suspect' States, 'good' States, and Nuclear Weapons States hosting fuel cycle centers. The continued use and further development of the SLA to customize safeguards for each State, including for States already under IS, is seen as central to effective and efficient safeguards for an expanding nuclear world.

  8. Instrumentation for international safeguards. Present and future

    International Nuclear Information System (INIS)

    On-site inspection supported by instrumentation has become the primary verification mode for international safeguards. The custom designed instrumentation for measurement, monitoring, sealing and containment has become the essential tools to support inspectors. At present, 76 instruments or instrumental systems are authorized for inspection use by IAEA. The global summary of IAEA safeguard statistics for 1992 is shown. Also field instrumentation use is shown. The Agency is in the transitional mode for optical surveillance from films to CCTV units. One-time use seals are predominantly employed, but the use of in-situ verifiable seals is increasing. It is noted that instrumentation has become an essential tool for safeguard effectiveness. Instrumentation is generally 'dumb' in the sense that it provides inspectors with specific information that must be interpreted and integrated with other data before drawing safeguard conclusion. The positive features of in-situ instrumentation are shown. A prime example of in-situ instruments is core discharge monitor. Also high count rate gamma spectrometry system and improved Cerenkov viewing device are described. As the equipment carried by inspectors to facilities, miniature CdTe detector probe is shown. Safeguard instrumentation needs for future and the instrumentation activities presently underway are described. (K.I.)

  9. Fundamentals of materials accounting for nuclear safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Pillay, K.K.S. (comp.)

    1989-04-01

    Materials accounting is essential to providing the necessary assurance for verifying the effectiveness of a safeguards system. The use of measurements, analyses, records, and reports to maintain knowledge of the quantities of nuclear material present in a defined area of a facility and the use of physical inventories and materials balances to verify the presence of special nuclear materials are collectively known as materials accounting for nuclear safeguards. This manual, prepared as part of the resource materials for the Safeguards Technology Training Program of the US Department of Energy, addresses fundamental aspects of materials accounting, enriching and complementing them with the first-hand experiences of authors from varied disciplines. The topics range from highly technical subjects to site-specific system designs and policy discussions. This collection of papers is prepared by more than 25 professionals from the nuclear safeguards field. Representing research institutions, industries, and regulatory agencies, the authors create a unique resource for the annual course titled ''Materials Accounting for Nuclear Safeguards,'' which is offered at the Los Alamos National Laboratory.

  10. SAFEGUARDS ENVELOPE: PREVIOUS WORK AND EXAMPLES

    Energy Technology Data Exchange (ETDEWEB)

    Richard Metcalf; Aaron Bevill; William Charlton; Robert Bean

    2008-07-01

    The future expansion of nuclear power will require not just electricity production but fuel cycle facilities such as fuel fabrication and reprocessing plants. As large reprocessing facilities are built in various states, they must be built and operated in a manner to minimize the risk of nuclear proliferation. Process monitoring has returned to the spotlight as an added measure that can increase confidence in the safeguards of special nuclear material (SNM). Process monitoring can be demonstrated to lengthen the allowable inventory period by reducing accountancy requirements, and to reduce the false positive indications. The next logical step is the creation of a Safeguards Envelope, a set of operational parameters and models to maximize anomaly detection and inventory period by process monitoring while minimizing operator impact and false positive rates. A brief example of a rudimentary Safeguards Envelope is presented, and shown to detect synthetic diversions overlaying a measured processing plant data set. This demonstration Safeguards Envelope is shown to increase the confidence that no SNM has been diverted with minimal operator impact, even though it is based on an information sparse environment. While the foundation on which a full Safeguards Envelope can be built has been presented in historical demonstrations of process monitoring, several requirements remain yet unfulfilled. Future work will require reprocessing plant transient models, inclusion of “non-traditional” operating data, and exploration of new methods of identifying subtle events in transient processes.

  11. The international scope of IAEA safeguards

    International Nuclear Information System (INIS)

    As a result of safeguards agreements under the Treaty on the Non-Proliferation of Nuclear Weapons (NPT) and with States not Party to that Treaty, the Agency's safeguards coverage today is very extensive. According to the best information officially available to the Agency, there are only five States in the world besides the nuclear-weapon States that have significant nuclear activities which are not subject to Agency safeguards, namely Egypt, India, Israel, South Africa and Spain. Nevertheless, any State that is not a Party to the NPT or the Treaty for the Prohibition of Nuclear Weapons in Latin America (Tlatelolco Treaty) is free, in the absence of treaty obligations, to build or otherwise acquire unsafeguarded nuclear plant. Furthermore, there are significant differences between the NPT safeguards agreements and those with States not Party to the NPT, not only with regard to scope (NPT agreements cover all peaceful nuclear activities in the State, which in practice means all nuclear activities, while non-NPT agreements so far only cover particular plants or supply agreements) but also in technical and legal approach (NPT agreements reflect important advances in safeguards concepts indicated in the Treaty itself). (author)

  12. Role of carbon monoxide in impaired endothelial function mediated by acute second-hand tobacco, incense, and candle smoke exposures.

    Science.gov (United States)

    Weber, Lynn P; Al-Dissi, Ahmad; Marit, Jordan S; German, Timothy N; Terletski, Sharilyn D

    2011-05-01

    The aim of this study was to determine if carbon monoxide (CO) is responsible for acute adverse cardiovascular effects of different sources of smoke: second-hand tobacco smoke (SHS), incense and candle smoke. Endothelial function was tested using flow-mediated dilation (FMD) in pigs and was shown to be sensitive to nitric oxide synthase blockade. Subsequent experiments showed that FMD was significantly impaired compared to sham-exposed pigs at 30 min after a 30-min exposure to all three sources of smoke. In contrast, SHS significantly increased systolic, diastolic and pulse pressures compared to sham-exposure, while both incense and candle smoke exposure had no effect. The FMD impairment correlated well with CO levels in the exposure chamber, but not total particulates or venous CO-hemoglobin. Therefore, this study suggests a gas phase component of smoke that accompanies CO, but not CO itself, is responsible for acute endothelial dysfunction after SHS, incense or candle smoke exposure.

  13. GRBs with exponential decay in one hundred seconds as standard candles for Cosmology

    CERN Document Server

    Nathanail, Antonios; Basilakos, Spyros

    2014-01-01

    We investigate a particular subclass of gamma-ray bursts whose prompt X-ray emission lasts for a few hundred seconds and shows a clear exponential decay over more than four orders of magnitude. We associate them with the electromagnetic spindown of the black hole that forms during the core collapse of a supermassive star. Their characteristic spindown timescale is inversely proportional to the square of the magnetic flux accumulated through their horizon. We show that these objects give-off roughly the same amount of energy in X-rays, and therefore, they may form standard candles for Cosmology.

  14. Planetary nebulae as standard candles. III - The distance to M81

    Science.gov (United States)

    Jacoby, George H.; Ciardullo, Robin; Booth, John; Ford, Holland C.

    1989-01-01

    The results of a survey for PN in the nearby Sb galaxy M81 are reported, including the identification of 185 PN candidates. A distance to M81 of 3.50 + or - 0.40 Mpc is derived using the methods outlined by Ciardullo, et al. (1989). This value compares very well with values derived using traditional methods. Based on this agreement, it is concluded that PN are as good as, or better than, other standard candles for deriving distances to galaxies beyond 10 Mpc.

  15. Comparison of the egg flotation and egg candling techniques for estimating incubation day of Canada Goose nests

    Science.gov (United States)

    Reiter, M.E.; Andersen, D.E.

    2008-01-01

    Both egg flotation and egg candling have been used to estimate incubation day (often termed nest age) in nesting birds, but little is known about the relative accuracy of these two techniques. We used both egg flotation and egg candling to estimate incubation day for Canada Geese (Branta canadensis interior) nesting near Cape Churchill, Manitoba, from 2000 to 2007. We modeled variation in the difference between estimates of incubation day using each technique as a function of true incubation day, as well as, variation in error rates with each technique as a function of the true incubation day. We also evaluated the effect of error in the estimated incubation day on estimates of daily survival rate (DSR) and nest success using simulations. The mean difference between concurrent estimates of incubation day based on egg flotation minus egg candling at the same nest was 0.85 ?? 0.06 (SE) days. The positive difference in favor of egg flotation and the magnitude of the difference in estimates of incubation day did not vary as a function of true incubation day. Overall, both egg flotation and egg candling overestimated incubation day early in incubation and underestimated incubation day later in incubation. The average difference between true hatch date and estimated hatch date did not differ from zero (days) for egg flotation, but egg candling overestimated true hatch date by about 1 d (true - estimated; days). Our simulations suggested that error associated with estimating the incubation day of nests and subsequently exposure days using either egg candling or egg flotation would have minimal effects on estimates of DSR and nest success. Although egg flotation was slightly less biased, both methods provided comparable and accurate estimates of incubation day and subsequent estimates of hatch date and nest success throughout the entire incubation period. ?? 2008 Association of Field Ornithologists.

  16. International safeguards for spent fuel storage

    International Nuclear Information System (INIS)

    This report analyzes the nonproliferation effectiveness and political and economic acceptability of prospective improvements in international safeguard techniques for LWR spent fuel storage. Although the applicability of item accounting considerably eases the safeguarding of stored spent fuel, the problem of verification is potentially serious. A number of simple gamma and neutron nondestructive assay techniques were found to offer considerable improvements, of a qualitative rather than quantitative nature, in verification-related data and information, and possess the major advantage of intruding very little on facility operations. A number of improved seals and monitors appear feasible as well, but improvements in the timeliness of detection will not occur unless the frequency of inspection is increased or a remote monitoring capability is established. Limitations on IAEA Safeguards resources and on the integration of results from material accounting and containment and surveillance remain problems

  17. Integrated international safeguards concepts for fuel reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Hakkila, E.A.; Gutmacher, R.G.; Markin, J.T.; Shipley, J.P.; Whitty, W.J.; Camp, A.L.; Cameron, C.P.; Bleck, M.E.; Ellwein, L.B.

    1981-12-01

    This report is the fourth in a series of efforts by the Los Alamos National Laboratory and Sandia National Laboratories, Albuquerque, to identify problems and propose solutions for international safeguarding of light-water reactor spent-fuel reprocessing plants. Problem areas for international safeguards were identified in a previous Problem Statement (LA-7551-MS/SAND79-0108). Accounting concepts that could be verified internationally were presented in a subsequent study (LA-8042). Concepts for containment/surveillance were presented, conceptual designs were developed, and the effectiveness of these designs was evaluated in a companion study (SAND80-0160). The report discusses the coordination of nuclear materials accounting and containment/surveillance concepts in an effort to define an effective integrated safeguards system. The Allied-General Nuclear Services fuels reprocessing plant at Barnwell, South Carolina, was used as the reference facility.

  18. Integrated international safeguards concepts for fuel reprocessing

    International Nuclear Information System (INIS)

    This report is the fourth in a series of efforts by the Los Alamos National Laboratory and Sandia National Laboratories, Albuquerque, to identify problems and propose solutions for international safeguarding of light-water reactor spent-fuel reprocessing plants. Problem areas for international safeguards were identified in a previous Problem Statement (LA-7551-MS/SAND79-0108). Accounting concepts that could be verified internationally were presented in a subsequent study (LA-8042). Concepts for containment/surveillance were presented, conceptual designs were developed, and the effectiveness of these designs was evaluated in a companion study (SAND80-0160). The report discusses the coordination of nuclear materials accounting and containment/surveillance concepts in an effort to define an effective integrated safeguards system. The Allied-General Nuclear Services fuels reprocessing plant at Barnwell, South Carolina, was used as the reference facility

  19. Conceptual design of integrated safeguards systems

    International Nuclear Information System (INIS)

    The Los Alamos Scientific Laboratory (LASL) is currently involved in the conceptual design of safeguards for generic facilities in the back-end of the nuclear fuel cycle (spent-fuel reprocessing, plutonium nitrate-to-oxide conversion, mixed-oxide fuel fabrication, plutonium scrap recovery, and waste handling). These studies are first steps aimed at eventually providing detailed designs of integrated safeguards systems to guide safeguards-related facility construction and/or modification. The purpose of this presentation is to describe the conceptual design process in terms of its definition, a systematic procedure for its implementation, some of the tools required, and an example of the results of a conceptual design. The value of conceptual design and its relationship to other facets of the complete facility design process are also discussed

  20. Beyond Human Capital Development: Balanced Safeguards Workforce Metrics and the Next Generation Safeguards Workforce

    International Nuclear Information System (INIS)

    Since its establishment in 2008, the Next Generation Safeguards Initiative (NGSI) has achieved a number of objectives under its five pillars: concepts and approaches, policy development and outreach, international nuclear safeguards engagement, technology development, and human capital development (HCD). As a result of these efforts, safeguards has become much more visible as a critical U.S. national security interest across the U.S. Department of Energy (DOE) complex. However, limited budgets have since created challenges in a number of areas. Arguably, one of the more serious challenges involves NGSI's ability to integrate entry-level staff into safeguards projects. Laissez fair management of this issue across the complex can lead to wasteful project implementation and endanger NGSI's long-term sustainability. The authors provide a quantitative analysis of this problem, focusing on the demographics of the current safeguards workforce and compounding pressures to operate cost-effectively, transfer knowledge to the next generation of safeguards professionals, and sustain NGSI safeguards investments.

  1. U.S. safeguards history and the evolution of safeguards research and development

    International Nuclear Information System (INIS)

    In discussing the U.S. safeguards history and the evolution of safeguards research and development, five significant eras are identified. The period ending January 1, 1947, may be called the first era. Safeguards as known today did not exist and the classic military approach of security protection applied. The second era covers the period from 1947 to 1954 (when the Atomic Energy Act was completely rewritten to accommodate the then foreseen Civil uses Program and international cooperation in peaceful uses of nuclear energy), and the first steps were taken by the Atomic Energy Commission to establish material accounting records for all source and fissionable materials on inventory. The third era covers the period 1954 through 1968, which focused on nuclear safeguards in its domestic activities and made major policy changes in its approach to material control and accountability. The fourth era, 1968 to 1972 saw a quantum jump in the recognition and need for a significant safeguards research and development program, answered by the formation of a safeguards technical support organization at Brookhaven National Laboratory and a safeguards Laboratory at Los Alamos Scientific Laboratory for the development and application of non-destructive assay technology. The fifth era had its beginning in 1972 with the burgeoning of international terrorism. The corresponding need for a strong physical protection research and development support program was responded to by the Sandia National Laboratory

  2. Study on an Integrated Sintered Metal Screen Moving Granular Bed Filter

    Institute of Scientific and Technical Information of China (English)

    吴晋沪; 王洋

    2004-01-01

    A new gas clean-up process called "integrated sintered metal screen moving granular bed" (ISMSMGB) for the integrated gasification combined cycle (IGCC) and pressured fluidized bed combustion (PFBC) was developed on the basis of a sintered metal candle filter and a cross-flow moving granular bed filter. This is a combination of the surface and deep bed filtering processes. A set of facilities was established and a series of cold model tests were carried out. The dust removal efficiency and the pressure drop of the filter were measured and analyzed. The results show that this process features the advantages of the moving bed for high capacity as well as high inlet dust load and the surface filter for high efficiency. Meanwhile, the granules moving downward cleans the cake on the screen surface, so that the system is operated at steady state.

  3. The evolution of information-driven safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Budlong-sylvester, Kory W [Los Alamos National Laboratory; Pilat, Joseph F [Los Alamos National Laboratory

    2010-10-14

    From the adoption of the Model Additional Protocol and integrated safeguards in the 1990s, to current International Atomic Energy Agency (IAEA) efforts to deal with cases of noncompliance, the question of how the Agency can best utilize all the information available to it remains of great interest and increasing importance. How might the concept of 'information-driven' safeguards (IDS) evolve in the future? The ability of the Agency to identify and resolve anomalies has always been important and has emerged as a core Agency function in recent years as the IAEA has had to deal with noncompliance in Iran and the Democratic People's Republic of Korea (DPRK). Future IAEA safeguards implementation should be designed with the goal of facilitating and enhancing this vital capability. In addition, the Agency should utilize all the information it possesses, including its in-house assessments and expertise, to direct its safeguards activities. At the State level, knowledge of proliferation possibilities is currently being used to guide the analytical activities of the Agency and to develop inspection plans. How far can this approach be extended? Does it apply across State boundaries? Should it dictate a larger fraction of safeguards activities? Future developments in IDS should utilize the knowledge resident within the Agency to ensure that safeguards resources flow to where they are most needed in order to address anomalies first and foremost, but also to provide greater confidence in conclusions regarding the absence of undeclared nuclear activities. The elements of such a system and related implementation issues are assessed in this paper.

  4. 20 years of the implementation of the safeguards agreements

    International Nuclear Information System (INIS)

    Peru has signed an INFIRC/153 type safeguards agreement with the IAEA in 1979. The paper describes the nuclear material under control and outlines the organization and the activities related to the implementation of the safeguards agreements

  5. Reactor monitoring and safeguards using antineutrino detectors

    CERN Document Server

    Bowden, N S

    2008-01-01

    Nuclear reactors have served as the antineutrino source for many fundamental physics experiments. The techniques developed by these experiments make it possible to use these very weakly interacting particles for a practical purpose. The large flux of antineutrinos that leaves a reactor carries information about two quantities of interest for safeguards: the reactor power and fissile inventory. Measurements made with antineutrino detectors could therefore offer an alternative means for verifying the power history and fissile inventory of a reactors, as part of International Atomic Energy Agency (IAEA) and other reactor safeguards regimes. Several efforts to develop this monitoring technique are underway across the globe.

  6. Insider safeguards effectiveness model (ISEM). User's guide

    International Nuclear Information System (INIS)

    A comprehensive presentation of the ISEM computer program is provided. ISEM was designed to evaluate the effectiveness of a fixed-site facility safeguards system in coping with the theft, sabotage, or dispersal of radiological material by a single person who has authorized access to the facility. This insider may be aided by a group of insiders who covertly degrade sensor systems. Each ISEM run evaluates safeguards system performance for a particular scenario specified by the user. The dispatching of guards following alarms and their interaction with the insider are explicitly treated by the model

  7. Analytical measurements for safeguarding large reprocessing facilities

    International Nuclear Information System (INIS)

    Verification analysis of samples taken at large reprocessing plants can be performed off site after shipment of the samples to a specialized laboratory of, more advantageously in terms of cost and timeliness, on site. The latter may be achieved either by using permanently installed equipment which is operated by an inspector or in fully equipped on-site laboratory. Analytical techniques suitable for determining uranium and plutonium isotopic compositions as well as the respective element concentrations, are applied. Experience with a number of these techniques has shown that effective analytical support in safeguarding large reprocessing plants can be provided to the safeguards authorities

  8. Guidance for States Implementing Comprehensive Safeguards Agreements and Additional Protocols

    International Nuclear Information System (INIS)

    This publication is aimed at enhancing States’ understanding of the safeguards obligations of both the State and the IAEA, and at improving the cooperation between States and the IAEA in safeguards implementation. It is principally intended for State or regional safeguards regulatory authorities and facility operators, and is a reference document that is supported by detailed guidance and examples in safeguards implementation practices presented in other publications in the series. (This version is the 2016 update.)

  9. Domestic safeguards: annual report to Congress, fiscal year 1978

    International Nuclear Information System (INIS)

    The annual report includes an assessment of the effectiveness and adequacy of safeguards at facilities and activities licensed by the Commission. The report details NRC's criteria for judging the adequacy of safeguards at fuel cycle facilities; the report also summarizes actions required by NRC at any fuel facility whose safeguards systems are judged to provide less than high assurance protection against our design threat. The report also contains a discussion of NRC's criteria for safeguards adequacy at nuclear reactors and for transportation activities

  10. Safeguards technology research and development at CIAE

    International Nuclear Information System (INIS)

    Full text: China Institute of Atomic Energy (CIAE) is a multi-disciplinary institute under the leadership of China National Nuclear Corporation (CNNC). The Laboratory of Technical Research for Nuclear Safeguards was established at CIAE in 1991 to develop safeguards technology and to provide technical assistance to competent authorities for nuclear material management and control, which became one of the key laboratories approved by CNNC in 1993. The main research works for safeguards at CIAE include: nuclear material control and accounting, facilities license review and assessment, domestic inspection, NDA and DA analysis, physical protection and technical training. Research and development of equipment and technique for safeguards has been continuing at CIAE. A variety of NDA equipment that has different resolution and analysis capability has been developed. Method of NDA measurement has been investigated for nuclear material with different characteristics. Mathematics method such as Monte Carlo simulation is applied in NDA. Advanced destructive analysis (DA) instrument is installed at laboratory of CIAE, such as TIMS, ICP-MS and electronic chemistry analyzing system. The high accuracy results of element analysis and isotopic analysis for nuclear material can be obtained. It is possible to measure the types and quantities of nuclear material in a given area by means of NDA and DA. Physical protection system has also been developed. It consists of access control and management, various alarm (including perimeter alarm, intrusion alarms, fire alarms), video and audio monitors, intercommunication set and central console. The system can meet technical requirement for safeguards of first rank. Nuclear material accounting is an important aspect of safeguards research at CIAE. The computer software related to material accounting has been developed. It is the important task for scientists at CIAE to design and review nuclear accounting systems in various facilities. For

  11. Unbiased constraints on the clumpiness of the Universe from standard candles

    Science.gov (United States)

    Li, Zhengxiang; Ding, Xuheng; Zhu, Zong-Hong

    2015-04-01

    We perform unbiased tests for the clumpiness of the Universe by confronting the Zel'dovich-Kantowski-Dyer-Roeder luminosity distance, which describes the effect of local inhomogeneities on the propagation of light with the observational one estimated from measurements of standard candles, i.e., type Ia supernovae (SNe Ia) and gamma-ray bursts (GRBs). Methodologically, we first determine the light-curve fitting parameters which account for distance estimation in SNe Ia observations and the luminosity/energy relations which are responsible for distance estimation of GRBs in the global fit to reconstruct the Hubble diagrams in the context of a clumpy Universe. Subsequently, these Hubble diagrams allow us to achieve unbiased constraints on the matter density parameter Ωm , as well as the clumpiness parameter η which quantifies the fraction of homogeneously distributed matter within a given light cone. At a 1 σ confidence level, the constraints are Ωm=0.34 ±0.02 and η =1.0 0-0.02+0.00 from the joint analysis. The results suggest that the Universe full of Friedman-Lemaître-Robertson-Walker fluid is favored by observations of standard candles with very high statistical significance. On the other hand, they may also indicate that the Zel'dovich-Kantowski-Dyer-Roeder approximation is a sufficiently accurate form to describe the effects of local homogeneity on the expanding Universe.

  12. Standard rulers, candles, and clocks from the low-redshift Universe

    CERN Document Server

    Heavens, Alan; Verde, Licia

    2014-01-01

    Assuming the existence of standard clocks, standard candles and standard rulers, we determine the length of the Baryon Acoustic Oscillation (BAO) feature, and the expansion history of the recent Universe, from low-redshift data only, in a relatively model-independent way. In this process we assume as little as possible, requiring only the cosmological principle, a metric theory of gravity, a smooth expansion history, and the existence of these standard objects; the rest is determined by the data. The data we use are a compilation of recent BAO data, Type \\OneA supernov\\ae\\ and ages of early-type galaxies. Making only these assumptions, we find for the first time that the standard ruler has a largely model-independent length of $101.9 \\pm 1.9 h^{-1}$ Mpc. We also find that the standard candle has a brightness consistent with determinations from supernov\\ae\\ alone, and that the inverse curvature radius of the Universe is weakly constrained and consistent with zero, independently of the gravity model, provided i...

  13. Emission characteristics of air pollutants from incense and candle burning in indoor atmospheres.

    Science.gov (United States)

    Manoukian, A; Quivet, E; Temime-Roussel, B; Nicolas, M; Maupetit, F; Wortham, H

    2013-07-01

    Volatile organic compounds (VOCs) and particles emitted by incense sticks and candles combustion in an experimental room have been monitored on-line and continuously with a high time resolution using a state-of-the-art high sensitivity-proton transfer reaction-mass spectrometer (HS-PTR-MS) and a condensation particle counter (CPC), respectively. The VOC concentration-time profiles, i.e., an increase up to a maximum concentration immediately after the burning period followed by a decrease which returns to the initial concentration levels, were strongly influenced by the ventilation and surface interactions. The obtained kinetic data set allows establishing a qualitative correlation between the elimination rate constants of VOCs and their physicochemical properties such as vapor pressure and molecular weight. The emission of particles increased dramatically during the combustion, up to 9.1(±0.2) × 10(4) and 22.0(±0.2) × 10(4) part cm(-3) for incenses and candles, respectively. The performed kinetic measurements highlight the temporal evolution of the exposure level and reveal the importance of ventilation and deposition to remove the particles in a few hours in indoor environments.

  14. Void effect analysis of Pb-208 of fast reactors with modified CANDLE burn-up scheme

    Energy Technology Data Exchange (ETDEWEB)

    Widiawati, Nina, E-mail: nina-widiawati28@yahoo.com; Su’ud, Zaki, E-mail: szaki@fi.itb.ac.id [Nuclear Physics and Biophysics Research Group, Faculty of Mathematics and Natural Science, Bandung Institute of Technology Jalan Ganesha 10, Bandung (Indonesia)

    2015-09-30

    Void effect analysis of Pb-208 as coolant of fast reactors with modified candle burn-up scheme has been conducted. Lead cooled fast reactor (LFR) is one of the fourth-generation reactor designs. The reactor is designed with a thermal power output of 500 MWt. Modified CANDLE burn-up scheme allows the reactor to have long life operation by supplying only natural uranium as fuel cycle input. This scheme introducing discrete region, the fuel is initially put in region 1, after one cycle of 10 years of burn up it is shifted to region 2 and region 1 is filled by fresh natural uranium fuel. The reactor is designed for 100 years with 10 regions arranged axially. The results of neutronic calculation showed that the void coefficients ranged from −0.6695443 % at BOC to −0.5273626 % at EOC for 500 MWt reactor. The void coefficients of Pb-208 more negative than Pb-nat. The results showed that the reactors with Pb-208 coolant have better level of safety than Pb-nat.

  15. A Double Candle-Flame-Shaped Solar Flare Observed by SDO and STEREO

    Science.gov (United States)

    Gou, T.; Liu, R.; Wang, Y.; Liu, K.; Zhuang, B.; Zhang, Q.; Liu, J.

    2015-12-01

    We investigate an M1.4 flare occurring on 2011 January 28 near the northwest solar limb. The flare loop system exhibits a double candle-flame configuration in SDO/AIA's hot passbands, sharing a much larger cusp-shaped structure. The results of DEM analysis show that each candle flame has a similar temperature distribution as the famous Tsuneta flare. STEREO-A provides us a view from directly above the flare, and in SECCHI/EUVI 195 Å the post-flare loops are observed to propagate eastward. We performed a 3D reconstruction of the pos-flare loops with AIA and EUVI data. With the aid of the squashing factor Q based on a potential extrapolation of the photospheric field, we recognized that the footpoints of the post-flare loops were slipping along high-Q lines on the photosphere, and the reconstructed loops share similarity with the filed lines that are traced starting from the high-Q lines. The heights of the loops increase as they slip horizontally eastward, giving the loop-top a velocity of about 10 km/s. An extremely large EUV late phase in Fe XVI 33.5 nm observed by SDO/EVE is suggested to be related to the slipping magnetic reconnection occurring in the quasi-separatrix layers (QSLs) whose photosheric footprints are featured by the high-Q lines.

  16. Development of a new 48Ca enrichment method and the CANDLES experiment

    Science.gov (United States)

    Kishimoto, Tadafumi

    2015-10-01

    CANDLES is a project to study double beta decay of 48Ca. CANDLES could become the most competitive experiment if we could have an efficient method to enrich 48Ca. We developed a new method for enrichment of large amount of calcium isotopes. The method is called Multi-Channel Counter-Current Electrophoresis (MCCCE) which can be found elsewhre. Essential point is the increase of the power density in the migration path. In MCCCE, ions migrate in multi-channels on a boron nitride (BN) plate by which substantial increase of the power density was achieved. We made a tiny prototype instrument with a 10 mm thick BN plate and obtained 3 for an enrichment factor for the ratio of abundance of 48Ca to 43Ca over that of natural abundance. It corresponds to 6 for the enrichment factor of 48Ca to 40Ca. Recently we obtained 10 for the enrichment factor by using 20 mm BN plate. This remarkably large enrichment factor demonstrates that the MCCCE is a realistic and promising method for the enrichment of large amount of ions. This method can be applied to many other elements and compounds. I will describe MCCCE and its effect on the study of double beta decay and other fields.

  17. Do All Candle-Flame-Shaped Flares Have the Same Temperature Distribution?

    Science.gov (United States)

    Gou, Tingyu; Liu, Rui; Wang, Yuming

    2015-08-01

    We performed a differential emission measure (DEM) analysis of candle-flame-shaped flares observed with the Atmospheric Imaging Assembly onboard the Solar Dynamic Observatory. The DEM profile of flaring plasmas generally exhibits a double peak distribution in temperature, with a cold component around log T≈6.2 and a hot component around log T≈7.0. Attributing the cold component mainly to the coronal background, we propose a mean temperature weighted by the hot DEM component as a better representation of flaring plasma than the conventionally defined mean temperature, which is weighted by the whole DEM profile. Based on this corrected mean temperature, the majority of the flares studied, including a confined flare with a double candle-flame shape sharing the same cusp-shaped structure, resemble the famous Tsuneta flare in temperature distribution, i.e., the cusp-shaped structure has systematically higher temperatures than the rounded flare arcade underneath. However, the M7.7 flare on 19 July 2012 poses a very intriguing violation of this paradigm: the temperature decreases with altitude from the tip of the cusp toward the top of the arcade; the hottest region is slightly above the X-ray loop-top source that is co-spatial with the emission-measure-enhanced region at the top of the arcade. This signifies that a different heating mechanism from the slow-mode shocks attached to the reconnection site operates in the cusp region during the flare decay phase.

  18. Void effect analysis of Pb-208 of fast reactors with modified CANDLE burn-up scheme

    Science.gov (United States)

    Widiawati, Nina; Su'ud, Zaki

    2015-09-01

    Void effect analysis of Pb-208 as coolant of fast reactors with modified candle burn-up scheme has been conducted. Lead cooled fast reactor (LFR) is one of the fourth-generation reactor designs. The reactor is designed with a thermal power output of 500 MWt. Modified CANDLE burn-up scheme allows the reactor to have long life operation by supplying only natural uranium as fuel cycle input. This scheme introducing discrete region, the fuel is initially put in region 1, after one cycle of 10 years of burn up it is shifted to region 2 and region 1 is filled by fresh natural uranium fuel. The reactor is designed for 100 years with 10 regions arranged axially. The results of neutronic calculation showed that the void coefficients ranged from -0.6695443 % at BOC to -0.5273626 % at EOC for 500 MWt reactor. The void coefficients of Pb-208 more negative than Pb-nat. The results showed that the reactors with Pb-208 coolant have better level of safety than Pb-nat.

  19. 16 CFR 314.3 - Standards for safeguarding customer information.

    Science.gov (United States)

    2010-01-01

    ... 16 Commercial Practices 1 2010-01-01 2010-01-01 false Standards for safeguarding customer... OF CONGRESS STANDARDS FOR SAFEGUARDING CUSTOMER INFORMATION § 314.3 Standards for safeguarding customer information. (a) Information security program. You shall develop, implement, and maintain...

  20. Waste isolation safeguards and security system. Volume 2. Bibliography

    International Nuclear Information System (INIS)

    The purpose of this study is to define the rationale and scope of the Waste Isolation System (WIS) safeguards system, to establish a set of proposed basic safeguards criteria, and to identify the areas requiring development of specific criteria and technology. The report also presents a proposed program schedule and provides an extensive bibliography, in volumes two and three of applicable reference safeguards documents

  1. Waste isolation safeguards and security system. Volume 3. Bibliography supplement

    International Nuclear Information System (INIS)

    The purpose of this study is to define the rationale and scope of the Waste Isolation System (WIS) safeguards system, to establish a set of proposed basic safeguards criteria, and to identify the areas requiring development of specific criteria and technology. The report also presents a proposed program schecule and provides an extensive bibliography in volumes two and three of applicable reference safeguards documents

  2. Safeguards instruments for Large-Scale Reprocessing Plants

    Energy Technology Data Exchange (ETDEWEB)

    Hakkila, E.A. [Los Alamos National Lab., NM (United States); Case, R.S.; Sonnier, C. [Sandia National Labs., Albuquerque, NM (United States)

    1993-06-01

    Between 1987 and 1992 a multi-national forum known as LASCAR (Large Scale Reprocessing Plant Safeguards) met to assist the IAEA in development of effective and efficient safeguards for large-scale reprocessing plants. The US provided considerable input for safeguards approaches and instrumentation. This paper reviews and updates instrumentation of importance in measuring plutonium and uranium in these facilities.

  3. Finnish nuclear verification (FINUVE) in support of IAEA safeguards

    International Nuclear Information System (INIS)

    Full text: Finland has two IAEA support programmes funded by the Ministry of Foreign Affairs. Those are the Finnish support programme for safeguards, FINSP, and the Finnish support programme for the IAEA Iraq Action Team. Both programmes are coordinated by STUK and several universities and research institutions participate in them. Within both programmes Environmental Sampling (ES) and Wide Area Environmental Sampling (WAES) technologies are developed. Both these techniques require chemical and radiochemical measurements. In order to utilize the whole Finnish experience in this field, the three institutions, STUK, VTT and HYRL, have signed a contract for cooperation within safeguards related analysis. The FINUVE contract states that these three institutes form a consortium to perform development work and if needed, participate in routine safeguards analytical work. The wide variety of analytical services is available on a commercial basis. The FINUVE organisation is very simple: it has a coordination group, which consists of a chairman from STUK and one participant from each organisation. These participants represent the analytical groups in each organisation. FINUVE, with STUK as the signatory, is a certified member of the IAEA Network of Analytical Laboratories, NWAL. FINUVE participated in an NWAL inter comparison for the analysis of bulk concentrations of fission products, uranium and plutonium isotopes in swipe samples. The results were quite good when compared with the expected values. In 2000 a new support programme task on particle analysis was started with the name Development of New Methods for Environmental Sample Analysis. Until now the major effort of FINUVE has been on the development of WAES methods. Since 1994 we have analysed environmental samples from field trials organised by the Agency. We have also done several theoretical studies on WAES technologies, in some cases by participating in the work of international working groups. In 1998 FINUVE

  4. Calculating uncertainties of safeguards indices: error propagation

    International Nuclear Information System (INIS)

    Statistical methods play an important role in making references about a MUF, shipper-receiver difference, operator-inspector difference, and other safeguards indices. This session considers the sources and types of measurement errors and treats a specific example to illustrate how the variance of MUF is calculated for the model plant

  5. 45 CFR 84.36 - Procedural safeguards.

    Science.gov (United States)

    2010-10-01

    ... HANDICAP IN PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Preschool, Elementary, and Secondary Education § 84.36 Procedural safeguards. A recipient that operates a public elementary or secondary education program or activity shall establish and implement, with respect to actions regarding...

  6. 45 CFR 605.36 - Procedural safeguards.

    Science.gov (United States)

    2010-10-01

    ... Preschool, Elementary, and Secondary Education § 605.36 Procedural safeguards. A recipient that operates a public elementary or secondary education program shall establish and implement, with respect to actions... the Education of the Handicapped Act is one means of meeting this requirement....

  7. Advanced Safeguards Approaches for New Fast Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Durst, Philip C.; Therios, Ike; Bean, Robert; Dougan, A.; Boyer, Brian; Wallace, Rick L.; Ehinger, Michael H.; Kovacic, Don N.; Tolk, K.

    2007-12-15

    This third report in the series reviews possible safeguards approaches for new fast reactors in general, and the ABR in particular. Fast-neutron spectrum reactors have been used since the early 1960s on an experimental and developmental level, generally with fertile blanket fuels to “breed” nuclear fuel such as plutonium. Whether the reactor is designed to breed plutonium, or transmute and “burn” actinides depends mainly on the design of the reactor neutron reflector and the whether the blanket fuel is “fertile” or suitable for transmutation. However, the safeguards issues are very similar, since they pertain mainly to the receipt, shipment and storage of fresh and spent plutonium and actinide-bearing “TRU”-fuel. For these reasons, the design of existing fast reactors and details concerning how they have been safeguarded were studied in developing advanced safeguards approaches for the new fast reactors. In this regard, the design of the Experimental Breeder Reactor-II “EBR-II” at the Idaho National Laboratory (INL) was of interest, because it was designed as a collocated fast reactor with a pyrometallurgical reprocessing and fuel fabrication line – a design option being considered for the ABR. Similarly, the design of the Fast Flux Facility (FFTF) on the Hanford Site was studied, because it was a successful prototype fast reactor that ran for two decades to evaluate fuels and the design for commercial-scale fast reactors.

  8. International safeguards: Accounting for nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Fishbone, L.G.

    1988-09-28

    Nuclear safeguards applied by the International Atomic Energy Agency (IAEA) are one element of the non-proliferation regime'', the collection of measures whose aim is to forestall the spread of nuclear weapons to countries that do not already possess them. Safeguards verifications provide evidence that nuclear materials in peaceful use for nuclear-power production are properly accounted for. Though carried out in cooperation with nuclear facility operators, the verifications can provide assurance because they are designed with the capability to detect diversion, should it occur. Traditional safeguards verification measures conducted by inspectors of the IAEA include book auditing; counting and identifying containers of nuclear material; measuring nuclear material; photographic and video surveillance; and sealing. Novel approaches to achieve greater efficiency and effectiveness in safeguards verifications are under investigation as the number and complexity of nuclear facilities grow. These include the zone approach, which entails carrying out verifications for groups of facilities collectively, and randomization approach, which entails carrying out entire inspection visits some fraction of the time on a random basis. Both approaches show promise in particular situations, but, like traditional measures, must be tested to ensure their practical utility. These approaches are covered on this report. 15 refs., 16 figs., 3 tabs.

  9. Applications of Virtual Reality to Nuclear Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Stansfield, S.

    1998-11-03

    This paper explores two potential applications of Virtual Reality (VR) to international nuclear safeguards: training and information organization and navigation. The applications are represented by two existing prototype systems, one for training nuclear weapons dismantlement and one utilizing a VR model to facilitate intuitive access to related sets of information.

  10. Innovative audit program for today's safeguards

    International Nuclear Information System (INIS)

    An internal safeguards audit program was developed and implemented at GE facilities to meet the need for effective audit and accurate, timely reporting to management. The concepts from which the program was evolved are summarized. The documentation and reporting mechanism has worked well for both the auditee and management

  11. 75 FR 32145 - Safeguarding Child Support Information

    Science.gov (United States)

    2010-06-07

    ... attorney who used a variety of tactics to collect child support that violated rules of professional...) created and expanded State and Federal Child Support Enforcement databases under title IV-D of the Social... require safeguarding measures for information contained in State and Federal databases, including...

  12. Non-proliferation policy and safeguards

    International Nuclear Information System (INIS)

    At the beginning of '90s the international community and IAEA have been confronted with serious problems related to the maintaining of the world non-proliferation policy. At the end of the cold war, rumors regarding Iraq's nuclear armament secret program and a new democracies' perception regarding nuclear safety have given a strong impetus toward reinforcing and redefining the safeguards systems. Today this system has got the most advanced and modern means for the detection of nuclear materials stealing and surreptitious production. At the same time with the implementation of the new additional model of safeguards agreements, every country developed an important contribution to end this period in which proliferation and threatening of nuclear weapons were a ruling feature on the international scene. The paper presents the principles of IAEA and national nuclear safeguards system. Mentioned are the techniques and equipment for nuclear safeguards control applied particularly at Cernavoda NPP and TRIGA reactor at IRN - Pitesti as well as those related to the evaluation of the plutonium content in the irradiated fuel. In Romania largely utilized was the program ORIGEN

  13. International safeguards: Accounting for nuclear materials

    International Nuclear Information System (INIS)

    Nuclear safeguards applied by the International Atomic Energy Agency (IAEA) are one element of the ''non-proliferation regime'', the collection of measures whose aim is to forestall the spread of nuclear weapons to countries that do not already possess them. Safeguards verifications provide evidence that nuclear materials in peaceful use for nuclear-power production are properly accounted for. Though carried out in cooperation with nuclear facility operators, the verifications can provide assurance because they are designed with the capability to detect diversion, should it occur. Traditional safeguards verification measures conducted by inspectors of the IAEA include book auditing; counting and identifying containers of nuclear material; measuring nuclear material; photographic and video surveillance; and sealing. Novel approaches to achieve greater efficiency and effectiveness in safeguards verifications are under investigation as the number and complexity of nuclear facilities grow. These include the zone approach, which entails carrying out verifications for groups of facilities collectively, and randomization approach, which entails carrying out entire inspection visits some fraction of the time on a random basis. Both approaches show promise in particular situations, but, like traditional measures, must be tested to ensure their practical utility. These approaches are covered on this report. 15 refs., 16 figs., 3 tabs

  14. Readability of Special Education Procedural Safeguards

    Science.gov (United States)

    Mandic, Carmen Gomez; Rudd, Rima; Hehir, Thomas; Acevedo-Garcia, Dolores

    2012-01-01

    This study focused on literacy-related barriers to understanding the rights of students with disabilities and their parents within the special education system. SMOG readability scores were determined for procedural safeguards documents issued by all state departments of education. The average reading grade level was 16; 6% scored in the high…

  15. Improving the Safeguardability of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    T. Bjornard; R. Bari; D. Hebditch; P. Peterson; M. Schanfein

    2009-07-01

    The application of a Safeguards-by-Design (SBD) process for new nuclear facilities has the potential to reduce security risks and proliferation hazards while improving the synergy of major design features and raising operational efficiency, in a world where significant expansion of nuclear energy use may occur. Correspondingly, the U.S. DOE’s Next Generation Safeguards Initiative (NGSI) includes objectives to contribute to international efforts to develop SBD, and to apply SBD in the development of new U.S. nuclear infrastructure. Here, SBD is defined as a structured approach to ensure the timely, efficient and cost effective integration of international safeguards and other nonproliferation barriers with national material control and accountability, physical protection, and safety objectives into the overall design process for a nuclear facility, from initial planning through design, construction and operation. The SBD process, in its simplest form, may be applied usefully today within most national regulatory environments. Development of a mature approach to implementing SBD requires work in the areas of requirements definition, design processes, technology and methodology, and institutionalization. The U.S. efforts described in this paper are supportive of SBD work for international safeguards that has recently been initiated by the IAEA with the participation of many stakeholders including member States, the IAEA, nuclear technology suppliers, nuclear utilities, and the broader international nonproliferation community.

  16. Antineutrino reactor safeguards - a case study

    CERN Document Server

    Christensen, Eric; Jaffke, Patrick

    2013-01-01

    Antineutrinos have been proposed as a means of reactor safeguards for more than 30 years and there has been impressive experimental progress in neutrino detection. In this paper we conduct, for the first time, a case study of the application of antineutrino safeguards to a real-world scenario - the North Korean nuclear crisis in 1994. We derive detection limits to a partial or full core discharge in 1989 based on actual IAEA safeguards access and find that two independent methods would have yielded positive evidence for a second core with very high confidence. To generalize our results, we provide detailed estimates for the sensitivity to the plutonium content of various types of reactors, including most types of plutonium production reactors, based on detailed reactor simulations. A key finding of this study is that a wide class of reactors with a thermal power of less than 0.1-1 GWth can be safeguarded achieving IAEA goals for quantitative sensitivity and timeliness with detectors right outside the reactor ...

  17. 7 CFR 956.66 - Safeguards.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 8 2010-01-01 2010-01-01 false Safeguards. 956.66 Section 956.66 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... Onions shipped, pursuant to §§ 956.63 and 956.64, from entering channels of trade for other than...

  18. 7 CFR 948.24 - Safeguards.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 8 2010-01-01 2010-01-01 false Safeguards. 948.24 Section 948.24 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... entering trade channels other than those authorized by regulations and by such rules as may be...

  19. 7 CFR 906.44 - Safeguards.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 8 2010-01-01 2010-01-01 false Safeguards. 906.44 Section 906.44 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... pursuant to § 906.41 or § 906.42 from entering channels of trade for other than the specific...

  20. 7 CFR 966.56 - Safeguards.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 8 2010-01-01 2010-01-01 false Safeguards. 966.56 Section 966.56 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... from entering channels of trade for other than the specific purpose authorized therefor, and...

  1. 7 CFR 945.56 - Safeguards.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 8 2010-01-01 2010-01-01 false Safeguards. 945.56 Section 945.56 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... prevent shipments pursuant to § 945.53 from entering channels of trade and other outlets for other...

  2. 7 CFR 946.55 - Safeguards.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 8 2010-01-01 2010-01-01 false Safeguards. 946.55 Section 946.55 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... channels of trade and other outlets for other than the specific purposes authorized therefor, and...

  3. 7 CFR 958.56 - Safeguards.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 8 2010-01-01 2010-01-01 false Safeguards. 958.56 Section 958.56 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... dehydrators into dehydrated onion products, from entering channels of trade for other than the...

  4. Using Process Load Cell Information for IAEA Safeguards at Enrichment Plants

    Energy Technology Data Exchange (ETDEWEB)

    Laughter, Mark D [ORNL; Whitaker, J Michael [ORNL; Howell, John [University of Glasgow

    2010-01-01

    Uranium enrichment service providers are expanding existing enrichment plants and constructing new facilities to meet demands resulting from the shutdown of gaseous diffusion plants, the completion of the U.S.-Russia highly enriched uranium downblending program, and the projected global renaissance in nuclear power. The International Atomic Energy Agency (IAEA) conducts verification inspections at safeguarded facilities to provide assurance that signatory States comply with their treaty obligations to use nuclear materials only for peaceful purposes. Continuous, unattended monitoring of load cells in UF{sub 6} feed/withdrawal stations can provide safeguards-relevant process information to make existing safeguards approaches more efficient and effective and enable novel safeguards concepts such as information-driven inspections. The IAEA has indicated that process load cell monitoring will play a central role in future safeguards approaches for large-scale gas centrifuge enrichment plants. This presentation will discuss previous work and future plans related to continuous load cell monitoring, including: (1) algorithms for automated analysis of load cell data, including filtering methods to determine significant weights and eliminate irrelevant impulses; (2) development of metrics for declaration verification and off-normal operation detection ('cylinder counting,' near-real-time mass balancing, F/P/T ratios, etc.); (3) requirements to specify what potentially sensitive data is safeguards relevant, at what point the IAEA gains on-site custody of the data, and what portion of that data can be transmitted off-site; (4) authentication, secure on-site storage, and secure transmission of load cell data; (5) data processing and remote monitoring schemes to control access to sensitive and proprietary information; (6) integration of process load cell data in a layered safeguards approach with cross-check verification; (7) process mock-ups constructed to provide

  5. Safeguards Guidance for Designers of Commercial Nuclear Facilities - International Safeguards Requirements for Uranium Enrichment Plants

    International Nuclear Information System (INIS)

    For the past two years, the United States National Nuclear Security Administration, Office of International Regimes and Agreements (NA-243), has sponsored the Safeguards-by-Design Project, through which it is hoped new nuclear facilities will be designed and constructed worldwide more amenable to nuclear safeguards. In the course of this project it was recognized that commercial designer/builders of nuclear facilities are not always aware of, or understand, the relevant domestic and international safeguards requirements, especially the latter as implemented by the International Atomic Energy Agency (IAEA). To help commercial designer/builders better understand these requirements, a report was prepared by the Safeguards-by-Design Project Team that articulated and interpreted the international nuclear safeguards requirements for the initial case of uranium enrichment plants. The following paper summarizes the subject report, the specific requirements, where they originate, and the implications for design and construction. It also briefly summarizes the established best design and operating practices that designer/builder/operators have implemented for currently meeting these requirements. In preparing the subject report, it is recognized that the best practices are continually evolving as the designer/builder/operators and IAEA consider even more effective and efficient means for meeting the safeguards requirements and objectives.

  6. Safeguards Guidance for Designers of Commercial Nuclear Facilities – International Safeguards Requirements for Uranium Enrichment Plants

    Energy Technology Data Exchange (ETDEWEB)

    Philip Casey Durst; Scott DeMuth; Brent McGinnis; Michael Whitaker; James Morgan

    2010-04-01

    For the past two years, the United States National Nuclear Security Administration, Office of International Regimes and Agreements (NA-243), has sponsored the Safeguards-by-Design Project, through which it is hoped new nuclear facilities will be designed and constructed worldwide more amenable to nuclear safeguards. In the course of this project it was recognized that commercial designer/builders of nuclear facilities are not always aware of, or understand, the relevant domestic and international safeguards requirements, especially the latter as implemented by the International Atomic Energy Agency (IAEA). To help commercial designer/builders better understand these requirements, a report was prepared by the Safeguards-by-Design Project Team that articulated and interpreted the international nuclear safeguards requirements for the initial case of uranium enrichment plants. The following paper summarizes the subject report, the specific requirements, where they originate, and the implications for design and construction. It also briefly summarizes the established best design and operating practices that designer/builder/operators have implemented for currently meeting these requirements. In preparing the subject report, it is recognized that the best practices are continually evolving as the designer/builder/operators and IAEA consider even more effective and efficient means for meeting the safeguards requirements and objectives.

  7. First Report of Veronica Rust by Puccinia veronicae-longifoliae in Minnesota on Veronica spicata Royal Candles

    Science.gov (United States)

    In September 2008, Veronica spicata Royal Candles plants showing foliar symptoms typical of a rust infection were brought to the Plant Disease Clinic at the University of Minnesota by a commercial nursery. A dark brown discoloration was apparent on the upper surface of the leaf with lighter brown pu...

  8. Study on core radius minimization for long life Pb-Bi cooled CANDLE burnup scheme based fast reactor

    Science.gov (United States)

    Afifah, Maryam; Miura, Ryosuke; Su'ud, Zaki; Takaki, Naoyuki; Sekimoto, H.

    2015-09-01

    Fast Breeder Reactor had been interested to be developed over the world because it inexhaustible source energy, one of those is CANDLE reactor which is have strategy in burn-up scheme, need not control roads for control burn-up, have a constant core characteristics during energy production and don't need fuel shuffling. The calculation was made by basic reactor analysis which use Sodium coolant geometry core parameter as a reference core to study on minimum core reactor radius of CANDLE for long life Pb-Bi cooled, also want to perform pure coolant effect comparison between LBE and sodium in a same geometry design. The result show that the minimum core radius of Lead Bismuth cooled CANDLE is 100 cm and 500 MWth thermal output. Lead-Bismuth coolant for CANDLE reactor enable to reduce much reactor size and have a better void coefficient than Sodium cooled as the most coolant for FBR, then we will have a good point in safety analysis.

  9. Study on core radius minimization for long life Pb-Bi cooled CANDLE burnup scheme based fast reactor

    Energy Technology Data Exchange (ETDEWEB)

    Afifah, Maryam, E-mail: maryam.afifah210692@gmail.com; Su’ud, Zaki [Nuclear Research Group, FMIPA, Bandung Institute of Technology Jl. Ganesha 10, Bandung 40132 (Indonesia); Miura, Ryosuke; Takaki, Naoyuki [Department of Nuclear Safety Engineering, Tokyo City University 1-28-1 Tamazutsumi, Setagaya, Tokyo 158-8557 (Japan); Sekimoto, H. [Emerritus Prof. of Research Laboratory for Nuclear Reactors, Tokyo Inst. of Technology (Japan)

    2015-09-30

    Fast Breeder Reactor had been interested to be developed over the world because it inexhaustible source energy, one of those is CANDLE reactor which is have strategy in burn-up scheme, need not control roads for control burn-up, have a constant core characteristics during energy production and don’t need fuel shuffling. The calculation was made by basic reactor analysis which use Sodium coolant geometry core parameter as a reference core to study on minimum core reactor radius of CANDLE for long life Pb-Bi cooled, also want to perform pure coolant effect comparison between LBE and sodium in a same geometry design. The result show that the minimum core radius of Lead Bismuth cooled CANDLE is 100 cm and 500 MWth thermal output. Lead-Bismuth coolant for CANDLE reactor enable to reduce much reactor size and have a better void coefficient than Sodium cooled as the most coolant for FBR, then we will have a good point in safety analysis.

  10. International Atomic Energy Agency safeguards after Iraq - some Austrailian perceptions

    International Nuclear Information System (INIS)

    Iraq's nuclear weapons development program used facilities and nuclear material separate from its safeguarded activities. To detect such a strategy the IAEA's safeguards inspectors need access to locations and information beyond that foreseen in NPT safeguards agreements. But the IAEA is short of money. And detecting undeclared activities could be expensive. If the IAEA can establish a capability to detect undeclared activities, then it might be able to save on regular safeguards. But it's important not to put the cart before the horse - effective safeguards must come first, savings second

  11. Waste isolation safeguards and security system. Volume 1. Scoping study

    International Nuclear Information System (INIS)

    The purpose of this study is to define the rationale and scope of the Waste Isolation System (WIS) safeguards system, to establish a set of proposed basic safeguards criteria, and to identify the areas requiring development of specific criteria and technology. The report also presents a proposed program schedule and provides an extensive bibliography of applicable reference safeguards documents. Volume one contains the following: glossary, system description; threat definition; safeguards regulations review - current and future; WIS safeguards criteria; assessment of criteria applicability and development requirements; and program plan

  12. Legal instruments related to the application of safeguards

    International Nuclear Information System (INIS)

    The legal framework of IAEA safeguards consists of a number of elements, not at all of which are documents. These elements include the Statute of the IAEA; treaties and supply agreements calling for verification of nonproliferation undertakings; the basic safeguards documents, the safeguards agreements themselves, along with the relevant protocols and subsidiary arrangements; and finally, the decisions, interpretations and practices of the Board of Governors. After a discussion of these elements the major differences between the various types of IAEA safeguards agreements are outlined. Finally the procedures involved in the initiation, negotiation, conclusion and amendment of safeguards agreements are described. (author)

  13. Addressing verification challenges. Proceedings of an international safeguards symposium

    International Nuclear Information System (INIS)

    The symposium on international safeguards, Addressing Verification Challenges, was held in Vienna from 16 to 20 October 2006, with the aim of assessing the challenges to the IAEA safeguards system that have emerged, or intensified, since the previous IAEA safeguards symposium in 2001. Some 500 nuclear safeguards and verification experts from more than 60 countries and international organizations attended the event. In all, 129 papers were presented in 21 sessions. There were 14 keynote speeches and 110 oral presentations. A total of 65 papers were presented as posters. In addition, 16 commercial suppliers of safeguards relevant equipment and technology presented their wares and capabilities. The symposium was organized by the IAEA in cooperation with the Institute of Nuclear Materials Management (INMM) and the European Safeguards Research and Development Association (ESARDA). The symposium provided an important forum at which related issues could be discussed, the IAEA could showcase some of its ongoing work and the experts present could provide inputs of fresh thinking. The IAEA Safeguards Symposium 2006 was developed to cover five topics: current challenges to the safeguards system, further strengthening of safeguards practices and approaches, improving the collection and analysis of safeguards information, advances in safeguards techniques and technology, and future challenges. These proceedings contain the addresses given at the opening session, the technical plenary session and the closing session. The summary provides an overview of the oral presentations at the 21 sessions of the symposium. Each individual paper is indexed separately

  14. SARP-II: Safeguards Accounting and Reports Program, Revised

    Energy Technology Data Exchange (ETDEWEB)

    Kempf, C.R.

    1994-03-01

    A computer code, SARP (Safeguards Accounting and Reports Program) which will generate and maintain at-facility safeguards accounting records, and generate IAEA safeguards reports based on accounting data input by the user, was completed in 1990 by the Safeguards, Safety, and Nonproliferation Division (formerly the Technical Support Organization) at Brookhaven National Laboratory as a task under the US Program of Technical Support to IAEA safeguards. The code was based on a State System of Accounting for and Control of Nuclear Material (SSAC) for off-load refueled power reactor facilities, with model facility and safeguards accounting regime as described in IAEA Safeguards Publication STR-165. Since 1990, improvements in computing capabilities and comments and suggestions from users engendered revision of the original code. The result is an updated, revised version called SARP-II which is discussed in this report.

  15. SARP-II: Safeguards Accounting and Reports Program, Revised

    International Nuclear Information System (INIS)

    A computer code, SARP (Safeguards Accounting and Reports Program) which will generate and maintain at-facility safeguards accounting records, and generate IAEA safeguards reports based on accounting data input by the user, was completed in 1990 by the Safeguards, Safety, and Nonproliferation Division (formerly the Technical Support Organization) at Brookhaven National Laboratory as a task under the US Program of Technical Support to IAEA safeguards. The code was based on a State System of Accounting for and Control of Nuclear Material (SSAC) for off-load refueled power reactor facilities, with model facility and safeguards accounting regime as described in IAEA Safeguards Publication STR-165. Since 1990, improvements in computing capabilities and comments and suggestions from users engendered revision of the original code. The result is an updated, revised version called SARP-II which is discussed in this report

  16. Broader use of information under IAEA Safeguards

    International Nuclear Information System (INIS)

    International Safeguards applied for more than 25 years consists of a complex control system based on nuclear material accountancy. The technical objective is to provide for 'the timely detection of diversion of significant quantities of nuclear material from peaceful nuclear activities to the manufacture of nuclear weapons or of other nuclear explosive devises or for purposes unknown, and deterrence of such diversion by the risk of early detection' (para. 28. INFCIRC 153). Each Non-Nuclear Weapon State party to the NPT undertakes to accept full-scope IAEA Safeguards to all nuclear material within the State's territory or under it's jurisdiction or control. The current Safeguards system is focused on declared facilities and activities. It involves the independent verifications of the States' declarations. The IAEA's effort to Strengthen International Safeguards include measures to increase the information provided by States on their nuclear programmes broader access to 'other information' and measures related to increased physical access to sites and to the effectiveness of that access. The general approach is to compare a State's declared nuclear activities with supplementary information available to the IAEA, and to find any apparent inconsistencies. This paper presents an overview of the sources of information available to the Agency and its use with the overall goal of detecting at a very early stage undeclared nuclear activities. The discovery of clandestine nuclear activities in Iraq shows that nuclear material accountancy alone cannot give the international community through IAEA safeguards, credible assurance that State party to comprehensive safeguards are in compliance with their obligations. Nuclear material accountancy, as traditionally practised, focuses on detecting the possible diversion of nuclear material declared to the IAEA. Accountancy cannot indicate whether a state has undeclared nuclear material or facilities, which might point to the

  17. Challenging curriculum. Training the IAEA international safeguards inspectorate

    International Nuclear Information System (INIS)

    Each year, the IAEA recruits a group of highly qualified specialists to join its experienced international team of safeguards inspectors. Their work will take them to nuclear facilities around the world, to utilize instrumentation and gather information for verifying national pledges that nuclear activities and materials under IAEA safeguards are exclusively used for peaceful purposes, and in those States which have signed a protocol in addition to their safeguards agreement, they will provide assurances that there are no undeclared nuclear activities or materials. Under more than 220 safeguards agreements with 139 States, the IAEA has served as the world's nuclear safeguards inspectorate for the past four decades. The Agency carries out verification activities at more than 900 facilities worldwide, conducting about 2200 inspections a year. Before the new inspectors take to the field, however, they enter the classroom - participating in an extensive series of IAEA training courses, workshops, and seminars. The courses comprehensively cover the nuclear fuel cycle, the IAEA's safeguards role and responsibilities, and the skills and competence that safeguards inspectors need to do their jobs effectively and efficiently. Once on the job, training reinforces the evolving safeguards mission. Under the Agency's 'enhanced' safeguards training curriculum, experienced inspectors participate in seminars and courses designed to upgrade their skills and keep them fully informed of safeguards developments with respect to, for example, legal responsibilities, technological capabilities, and inspection procedures. The enhanced curriculum was developed in response to the IAEA's increasing safeguards responsibilities. The system has been strengthened in many ways since 1991, particularly for detecting any undeclared nuclear material and activities that should have been declared by a State under its safeguards agreement. This article presents an overview of the IAEA's safeguards

  18. Safeguards techniques and equipment. 2003 ed

    International Nuclear Information System (INIS)

    The 1990s saw significant non-proliferation related developments in the world, resulting in a new period of safeguards development. Over several years an assessment was made of how to strengthen the effectiveness and improve the efficiency of IAEA safeguards. In May 1997 this culminated in the adoption by the IAEA Board of Governors of a Protocol Additional to Safeguards Agreements which significantly broadens the role of IAEA safeguards. As a consequence, the IAEA safeguards system entered a new era. In 1997 the IAEA began to publish a new series of booklets on safeguards, called the International Nuclear Verification Series (NVS). The objective of these booklets was to help in explaining IAEA safeguards, especially the new developments in safeguards, particularly for facility operators and government officers involved with these topics. The current booklet, which is a revision and update of IAEA/NVS/1, is intended to give a full and balanced description of the techniques and equipment used for both nuclear material accountancy and containment and surveillance measures, and for the new safeguards measure of environmental sampling. A completely new section on data security has been added to describe the specific features that are included in installed equipment systems in order to ensure the authenticity and confidentiality of information. As new verification measures continue to be developed the material in this booklet will be periodically reviewed and updated versions issued. The basic verification measure used by the IAEA is nuclear material accountancy. In applying nuclear material accountancy, IAEA safeguards inspectors make independent measurements to verify quantitatively the amount of nuclear material presented in the State's accounts. For this purpose, inspectors count items (e.g. fuel assemblies, bundles or rods, or containers of powdered compounds of uranium or plutonium) and measure attributes of these items during their inspections using non

  19. Smart structures for application in ceramic barrier filter technology. Final report, August 1991--August 1994

    Energy Technology Data Exchange (ETDEWEB)

    Weinstein, S.J.; Lippert, T.E

    1994-12-01

    High temperature optical fiber sensors were developed to measure the in-service stressing that occurs in ceramic barrier filter systems. The optical fiber sensors were based on improvements to the sensor design developed under the DOE/METC Smart Structures for Fossil Energy Applications contract no. DE-AC21-89MC25159. In-house application testing of these sensors on both candle and cross-flow filters were performed in the Westinghouse Science and Technology Center High-Temperature, High-Pressure Filter Test Facility and the results analyzed. This report summarizes the sensor developments, methods to apply the sensors to the filters for in-situ testing, and the test results from the four in-house tests that were performed.

  20. Numerical Study of the Effects of the Face Velocity on Ceramic Filter

    Institute of Scientific and Technical Information of China (English)

    Seo,Taewon

    1998-01-01

    Time-averaged explicit Navier-Stokes equations with the modified Darcy's law for the three-dimensional cylindrical flow field were formulated to the problem.Numerical investigation of the effects of the face velocity on ceramic candle filter was executed in three-dimensional turbulent flow field.It is found that the flow in the vessel is pushed toward the filter region by the pressure difference between inside and outside of the filter due to the viscosity and inertial resistance.It is also found that the pressure drop is directly proportional to the flow rate and the slope of the pressure drop will be mitigated when the thickness of the filter cake(δ)is larger than 10mm.

  1. Long-term evaluation of the performance of four point-of-use water filters.

    Science.gov (United States)

    Pérez-Vidal, Andrea; Diaz-Gómez, Jaime; Castellanos-Rozo, Jose; Usaquen-Perilla, Olga Lucía

    2016-07-01

    Despite technological advances water supply quality and poor access to safe water remain a major problem in developing countries, especially in rural areas. Point-of-use (POU) water treatment has been shown to be a viable option to produce safe drinking water quality. The aim of this study was to evaluate, under laboratory conditions over 14 months, the performance of four household filtration systems: membrane filter (MF), one-candle ceramic filter (1CCF), two-candle ceramic filter (2CCF) and pot ceramic filter (PCF). The evaluation was made using spiked water having the required concentrations of turbidity, Escherichia coli and Total Dissolved Solids (TDS). The results show that all systems have high removal efficiencies for turbidity (98-99%), and E. coli 4-5 Log Reduction Value (LRV). The poorest efficiency was for TDS (9-18%). The MF and the CCF displayed no significant difference in efficiencies for these parameters. The PCF had less significant differences for turbidity removal than the other systems. The average filtration rate for all systems decreased during the operation time. The CPF showed the major potential to be used in rural communities mainly for its low operational level and maintenance requirements as well as its local craftsmanship. It was observed that the efficiency of the systems is highly sensitive to cleaning and maintenance activities and therefore, the system sustainability will depend considerably on the training and education of the potential users.

  2. Long-term evaluation of the performance of four point-of-use water filters.

    Science.gov (United States)

    Pérez-Vidal, Andrea; Diaz-Gómez, Jaime; Castellanos-Rozo, Jose; Usaquen-Perilla, Olga Lucía

    2016-07-01

    Despite technological advances water supply quality and poor access to safe water remain a major problem in developing countries, especially in rural areas. Point-of-use (POU) water treatment has been shown to be a viable option to produce safe drinking water quality. The aim of this study was to evaluate, under laboratory conditions over 14 months, the performance of four household filtration systems: membrane filter (MF), one-candle ceramic filter (1CCF), two-candle ceramic filter (2CCF) and pot ceramic filter (PCF). The evaluation was made using spiked water having the required concentrations of turbidity, Escherichia coli and Total Dissolved Solids (TDS). The results show that all systems have high removal efficiencies for turbidity (98-99%), and E. coli 4-5 Log Reduction Value (LRV). The poorest efficiency was for TDS (9-18%). The MF and the CCF displayed no significant difference in efficiencies for these parameters. The PCF had less significant differences for turbidity removal than the other systems. The average filtration rate for all systems decreased during the operation time. The CPF showed the major potential to be used in rural communities mainly for its low operational level and maintenance requirements as well as its local craftsmanship. It was observed that the efficiency of the systems is highly sensitive to cleaning and maintenance activities and therefore, the system sustainability will depend considerably on the training and education of the potential users. PMID:27105031

  3. Model-independent estimations for the curvature from standard candles and clocks

    CERN Document Server

    Li, Zhengxiang; Liao, Kai; Zhu, Zong-Hong

    2016-01-01

    Model-independent estimations for the spatial curvature not only provide a test for the fundamental Copernican principle assumption, but also can effectively break the degeneracy between curvature and dark energy properties. In this paper, we propose to achieve model-independent constraints on the spatial curvature from observations of standard candles and standard clocks, without assuming any fiducial cosmology and other priors. We find that, for the popular Union2.1 type Ia supernovae (SNe Ia ) observations, the spatial curvature is constrained to be $\\Omega_K=-0.045_{-0.172}^{+0.176}$. For the latest joint light-curve analysis (JLA) of SNe Ia observations, we obtain $\\Omega_K=-0.140_{-0.158}^{+0.161}$. It is suggested that these results are in excellent agreement with the spatially flat Universe. Moreover, compared to other approaches aiming for model-independent estimations of spatial curvature, this method also achieves constraints with competitive precision.

  4. Planetary nebulae as standard candles. IV - A test in the Leo I group

    Science.gov (United States)

    Ciardullo, Robin; Jacoby, George H.; Ford, Holland C.

    1989-01-01

    In this paper, PN are used to determine accurate distances to three galaxies in the Leo I group - The E0 giant elliptical NGC 3379, its optical companion, the SB0 spiral NGC 3384, and the smaller E6 elliptical NGC 3377. In all three galaxies, the luminosity-specific PN number densities are roughly the same, and the derived stellar death rates are in remarkable agreement with the predictions of stellar evolution theory. It is shown that the shape of the forbidden O III 5007 A PN luminosity function is the same in each galaxy and indistinguishable from that observed in M31 and M81. It is concluded that the PN luminosity function is an excellent standard candle for early-type galaxies.

  5. The luminosity function of galactic X-ray sources - A cutoff and a 'standard candle'

    Science.gov (United States)

    Margon, B.; Ostriker, J. P.

    1973-01-01

    Analysis of the 2- to 10-kev luminosity distribution of 36 X-ray sources in the Local Group having known or estimated distances, showing that there exists a luminosity cutoff of approximately 10 to the 37.7th ergs/sec in agreement with the theoretical (Eddington) limit for the luminosity of an approximately 1 solar mass star. Furthermore, among the complete sample of high-luminosity sources, there appears to be a statistically significant group of X-ray 'standard candles' at (within less than 0.8 mag) the critical luminosity. This finding (which is in agreement with the self-consistent mass flow accretion models) presents the possibility that X-ray sources may be used as extragalactic distance indicators in the next generation of X-ray astronomy experiments.

  6. Impact of small-scale inhomogeneities on observations of standard candles

    Science.gov (United States)

    Iwata, Kengo; Yoo, Chul-Moon

    2015-02-01

    We investigate the effect of small-scale inhomogeneities on standard candle observations, such as type-Ia supernovae (SNe) observations. The existence of the small-scale inhomogeneities may cause a tension between SNe observations and other observations with larger-diameter sources, such as the cosmic microwave background (CMB) observation. To clarify the impact of the small-scale inhomogeneities, we use the Dyer-Roeder approach. We determined the smoothness parameter α(z) as a function of the redshift z so as to compensate the deviation of cosmological parameters for SNe from those for CMB. The range of the deviation which can be compensated by the smoothness parameter α(z) satisfying 0≤α(z)≤1 is reported. Our result suggests that the tension may give us the information of the small-scale inhomogeneities through the smoothness parameter.

  7. Power flattening on modified CANDLE small long life gas-cooled fast reactor

    Energy Technology Data Exchange (ETDEWEB)

    Monado, Fiber [Nuclear Physics and Biophysics Research Group, Dept. of Physics, Faculty of Mathematics and Natural Sciences, Bandung Institute of Technology, Bandung, Indonesia and Dept. of Physics, Faculty of Mathematics and Natural Sciences, Sriwijaya University (Indonesia); Su' ud, Zaki; Waris, Abdul; Basar, Khairul [Nuclear Physics and Biophysics Research Group, Dept. of Physics, Faculty of Mathematics and Natural Sciences, Bandung Institute of Technology, Bandung (Indonesia); Ariani, Menik [Dept. of Physics, Faculty of Mathematics and Natural Sciences, Sriwijaya University (Indonesia); Sekimoto, Hiroshi [CRINES, Tokyo Institute of Technology, O-okoyama, Meguro-ku, Tokyo 152-8550 (Japan)

    2014-09-30

    Gas-cooled Fast Reactor (GFR) is one of the candidates of next generation Nuclear Power Plants (NPPs) that expected to be operated commercially after 2030. In this research conceptual design study of long life 350 MWt GFR with natural uranium metallic fuel as fuel cycle input has been performed. Modified CANDLE burn-up strategy with first and second regions located near the last region (type B) has been applied. This reactor can be operated for 10 years without refuelling and fuel shuffling. Power peaking reduction is conducted by arranging the core radial direction into three regions with respectively uses fuel volume fraction 62.5%, 64% and 67.5%. The average power density in the modified core is about 82 Watt/cc and the power peaking factor decreased from 4.03 to 3.43.

  8. The charge-asymmetric nonlocally-determined local-electric (CANDLE) solvation model

    CERN Document Server

    Sundararaman, Ravishankar

    2014-01-01

    Many important applications of electronic structure methods involve molecules or solid surfaces in a solvent medium. Since explicit treatment of the solvent in such methods is usually not practical, calculations often employ continuum solvation models to approximate the effect of the solvent. Previous solvation models either involve a parametrization based on atomic radii, which limits the class of applicable solutes, or based on solute electron density, which is more general but less accurate, especially for charged systems. We develop an accurate and general solvation model that includes a cavity that is a nonlocal functional of both solute electron density and potential, local dielectric response on this nonlocally-determined cavity, and nonlocal approximations to the cavity-formation and dispersion energies. The dependence of the cavity on the solute potential enables an explicit treatment of the solvent charge asymmetry. With only three parameters per solvent, this `CANDLE' model simultaneously reproduce...

  9. Candle soot-based super-amphiphobic coatings resist protein adsorption.

    Science.gov (United States)

    Schmüser, Lars; Encinas, Noemi; Paven, Maxime; Graham, Daniel J; Castner, David G; Vollmer, Doris; Butt, Hans Jürgen; Weidner, Tobias

    2016-01-01

    Super nonfouling surfaces resist protein adhesion and have a broad field of possible applications in implant technology, drug delivery, blood compatible materials, biosensors, and marine coatings. A promising route toward nonfouling surfaces involves liquid repelling architectures. The authors here show that soot-templated super-amphiphobic (SAP) surfaces prepared from fluorinated candle soot structures are super nonfouling. When exposed to bovine serum albumin or blood serum, x-ray photoelectron spectroscopy and time of flight secondary ion mass spectrometry analysis showed that less than 2 ng/cm(2) of protein was adsorbed onto the SAP surfaces. Since a broad variety of substrate shapes can be coated by soot-templated SAP surfaces, those are a promising route toward biocompatible materials design. PMID:27460261

  10. Polymer-based candle-shaped microneedle electrodes for electroencephalography on hairy skin

    Science.gov (United States)

    Arai, Miyako; Kudo, Yuta; Miki, Norihisa

    2016-06-01

    In this paper, we report on the optimization of the shape of dry microneedle electrodes for electroencephalography (EEG) on hairy locations and compare the electrodes we developed with conventional wet electrodes. We propose the use of SU-8-based candle-shaped microneedle electrodes (CMEs), which have pillars of 1.0 mm height and 0.4 mm diameter with a gap of 0.43 mm between pillars. Microneedles are formed on the top of the pillars. The shape was determined by how well the pillars can avoid hairs and support the microneedles to penetrate through the stratum corneum. The skin–electrode contact impedances of the fabricated CMEs were found to be higher and less stable than those of conventional wet electrodes. However, the CMEs successfully acquired signals with qualities as good as those of conventional wet electrodes. Given the usability of the CMEs, which do not require skin preparation or gel, they are promising alternatives to conventional wet electrodes.

  11. 多管陶瓷对过滤器内耦合效应数值模拟%Numerical Investigation of Coupling Effect in Multipipe Ceramic Filter Vessel

    Institute of Scientific and Technical Information of China (English)

    李海霞; 姬忠礼; 吴小林; CHOI Joo-Hong

    2008-01-01

    The Reynolds stress transport model and the Eulerian two-fluid model provided by the FLUENT code were applied to evaluate the gas-particle two-phase flow in the ceramic filter vessel.The ceramic filter vessel contains six candle filters.which are arranged in the form of equilateral hexagon.The variation of the areal density of the filter cake during the filtration and the back.pulse process were analyzed.The coupling effect between filters.gas and solid,filtration and pulse cleaning process were investigated,respectively.The numerical results show a good approach to predict the particle distribution in the vessel and the particle deposition on the filter element.This study provides the base for the intensive study on the analysis of the gas-particle flow in the filter vessel.

  12. Temperature and Electron Density Diagnostics of a Candle-flame-shaped Flare

    Science.gov (United States)

    Guidoni, S. E.; McKenzie, D. E.; Longcope, D. W.; Plowman, J. E.; Yoshimura, K.

    2015-02-01

    Candle-flame-shaped flares are archetypical structures that provide indirect evidence of magnetic reconnection. A flare resembling Tsuneta's famous 1992 candle-flame flare occurred on 2011 January 28; we present its temperature and electron density diagnostics. This flare was observed with Solar Dynamics Observatory/Atmospheric Imaging Assembly (SDO/AIA), Hinode/X-Ray Telescope (XRT), and Solar Terrestrial Relations Observatory Ahead (STEREO-A)/Extreme Ultraviolet Imager, resulting in high-resolution, broad temperature coverage, and stereoscopic views of this iconic structure. The high-temperature images reveal a brightening that grows in size to form a tower-like structure at the top of the posteruption flare arcade, a feature that has been observed in other long-duration events. Despite the extensive work on the standard reconnection scenario, there is no complete agreement among models regarding the nature of this high-intensity elongated structure. Electron density maps reveal that reconnected loops that are successively connected at their tops to the tower develop a density asymmetry of about a factor of two between the two legs, giving the appearance of "half-loops." We calculate average temperatures with a new fast differential emission measure (DEM) method that uses SDO/AIA data and analyze the heating and cooling of salient features of the flare. Using STEREO observations, we show that the tower and the half-loop brightenings are not a line-of-sight projection effect of the type studied by Forbes & Acton. This conclusion opens the door for physics-based explanations of these puzzling, recurrent solar flare features, previously attributed to projection effects. We corroborate the results of our DEM analysis by comparing them with temperature analyses from Hinode/XRT.

  13. TEMPERATURE AND ELECTRON DENSITY DIAGNOSTICS OF A CANDLE-FLAME-SHAPED FLARE

    Energy Technology Data Exchange (ETDEWEB)

    Guidoni, S. E. [NASA Goddard Space Flight Center/CUA, Code 674, 8800 Greenbelt Road, Greenbelt, MD 20771 (United States); McKenzie, D. E.; Longcope, D. W.; Yoshimura, K. [Department of Physics, Montana State University, Bozeman, MT 59717-3840 (United States); Plowman, J. E., E-mail: silvina.e.guidoni@nasa.gov [High Altitude Observatory, National Center for Atmospheric Research P.O. Box 3000, Boulder, CO 80307-3000 (United States)

    2015-02-10

    Candle-flame-shaped flares are archetypical structures that provide indirect evidence of magnetic reconnection. A flare resembling Tsuneta's famous 1992 candle-flame flare occurred on 2011 January 28; we present its temperature and electron density diagnostics. This flare was observed with Solar Dynamics Observatory/Atmospheric Imaging Assembly (SDO/AIA), Hinode/X-Ray Telescope (XRT), and Solar Terrestrial Relations Observatory Ahead (STEREO-A)/Extreme Ultraviolet Imager, resulting in high-resolution, broad temperature coverage, and stereoscopic views of this iconic structure. The high-temperature images reveal a brightening that grows in size to form a tower-like structure at the top of the posteruption flare arcade, a feature that has been observed in other long-duration events. Despite the extensive work on the standard reconnection scenario, there is no complete agreement among models regarding the nature of this high-intensity elongated structure. Electron density maps reveal that reconnected loops that are successively connected at their tops to the tower develop a density asymmetry of about a factor of two between the two legs, giving the appearance of ''half-loops''. We calculate average temperatures with a new fast differential emission measure (DEM) method that uses SDO/AIA data and analyze the heating and cooling of salient features of the flare. Using STEREO observations, we show that the tower and the half-loop brightenings are not a line-of-sight projection effect of the type studied by Forbes and Acton. This conclusion opens the door for physics-based explanations of these puzzling, recurrent solar flare features, previously attributed to projection effects. We corroborate the results of our DEM analysis by comparing them with temperature analyses from Hinode/XRT.

  14. Overview of the Facility Safeguardability Analysis (FSA) Process

    Energy Technology Data Exchange (ETDEWEB)

    Bari, Robert A.; Hockert, John; Wonder, Edward F.; Johnson, Shirley J.; Wigeland, Roald; Zentner, Michael D.

    2011-10-10

    The safeguards system of the International Atomic Energy Agency (IAEA) provides the international community with credible assurance that a State is fulfilling its nonproliferation obligations. The IAEA draws such conclusions from the evaluation of all available information. Effective and cost-efficient IAEA safeguards at the facility level are, and will remain, an important element of this “State-level” approach. Efficiently used, the Safeguards by Design (SBD) methodologies , , , now being developed can contribute to effective and cost-efficient facility-level safeguards. The Facility Safeguardability Assessment (FSA) introduced here supports SBD in three areas. 1. It describes necessary interactions between the IAEA, the State regulator, and the owner / designer of a new or modified facility to determine where SBD efforts can be productively applied, 2. It presents a screening approach intended to identify potential safeguard issues for; a) design changes to existing facilities; b) new facilities similar to existing facilities with approved safeguards approaches, and c) new designs, 3. It identifies resources (the FSA toolkit), such as good practice guides, design guidance, and safeguardability evaluation methods that can be used by the owner/designer to develop solutions for potential safeguards issues during the interactions with the State regulator and IAEA. FSA presents a structured framework for the application of the SBD tools developed in other efforts. The more a design evolves, the greater the probability that new safeguards issues could be introduced. Likewise, for first-of-a-kind facilities or research facilities that involve previously unused processes or technologies, it is reasonable to expect that a number of possible safeguards issues might exist. Accordingly, FSA is intended to help the designer and its safeguards experts identify early in the design process: • Areas where elements of previous accepted safeguards approach(es) may be applied

  15. Integrating security analysis and safeguards software engineering

    Energy Technology Data Exchange (ETDEWEB)

    Spencer, D.D.; Axline, R.M.

    1989-01-01

    These initiatives will work together to provide more secure safeguards software, as well as other critical systems software. The resulting design tools and methodologies, the evolving guidelines for software security, and the adversary-resistant software components will be applied to the software design at each stage to increase the design's inherent security and to make the design easier to analyze. The resident hardware monitor or other architectural innovations will provide complementary additions to the design to remove some of the burden of security from the software. The security analysis process, supported by new analysis methodologies and tools, will be applied to the software design as it evolves in an attempt to identify and remove vulnerabilities at the earliest possible point in the safeguards system life cycle. The result should be better and more verifiably secure software systems.

  16. Safeguards in Prototype Fast Breeder Reactor Monju

    International Nuclear Information System (INIS)

    The assemblies loaded in the core and stored in the ex-vessel storage tank (EVST) are in liquid sodium in the Japanese prototype fast breeder reactor (FBR) Monju. Since it is difficult to apply a direct verification procedure for the fuel assemblies in these areas, a dual containment and surveillance system consisting of two monitoring devices such as surveillance camera and radiation monitor that are functionally independent has been applied. In addition, the Monju Remote Monitoring System was developed to strengthen the continuous surveillance and to reduce the load of the inspection activities. Furthermore, the ex-vessel transfer machine radiation monitor (EVRM) and the exit gate monitor (EXGM) were upgraded to strengthen the monitoring of spent blanket fuel assemblies and to improve the reliability of distinguishing between fuel assemblies and non-fuel items. As the result, the integrated safeguards was introduced in November 2009, and the effective safeguards activities have been implemented in Monju. (author)

  17. Design of safeguards systems for authentication

    International Nuclear Information System (INIS)

    To permit valid conclusions to be drawn from safeguards data, it is essential that this data is known to be authentic. That is, it must be known that the data originated from the intended source, that the data was not changed in transit, and that it is not a repeat or delayed copy of previous data. Safeguards systems and equipment should be designed with authentication included, instead of attempting to add security later. Failure to integrate authentication measures early in the design results in systems that are expensive or possibly impossible to deploy securely. This paper gives some of the factors that should be considered and some of the methods that can be employed for ensuring high security while minimizing cost. The paper is a compilation of some of the lessons learned by the authors during many years of working with the authentication of these systems. (author)

  18. Authentication in the context of international safeguards

    International Nuclear Information System (INIS)

    The International atomic Energy Agency held its first Advisory Group meeting on the subject of authentication in 1981. This meeting concentrated on the application of authentication to in-plant Non-Destructive Assay equipment supplied by the Facility Operator/State. In the decade since this meeting, a considerable amount of interest has developed over the use of authentication technology as a vital element of effective International Safeguards. Attendant with this interest, confusion has developed over the meaning and the need for the application of the technology as it exists today, and it may exist in the future. This paper addresses the subject of authentication, with emphasis on its basic definition and the applications of authentication technology in International Safeguards

  19. Status and trends of safeguards equipment development

    International Nuclear Information System (INIS)

    Meeting the technical and logistical challenges of international safeguards instrumentation has been a major concern since the first safeguards inspection in the early 1960s. This concern and the related activities have been pursued vigorously since the inception of Member State Support Programs in 1976. The International Atomic Energy Agency (IAEA), with the vital and crucial assistance of member states, has strived toward reliable, credible instrumentation that can be directed toward the various specific applications encountered in the nuclear fuel cycle. This paper provides a status report on agency instrumentation as of 1993 and lists some of the new, perhaps even more formidable, challenges and trends that are expected to be encountered over the next few years

  20. Generalised Filtering

    Directory of Open Access Journals (Sweden)

    Karl Friston

    2010-01-01

    Full Text Available We describe a Bayesian filtering scheme for nonlinear state-space models in continuous time. This scheme is called Generalised Filtering and furnishes posterior (conditional densities on hidden states and unknown parameters generating observed data. Crucially, the scheme operates online, assimilating data to optimize the conditional density on time-varying states and time-invariant parameters. In contrast to Kalman and Particle smoothing, Generalised Filtering does not require a backwards pass. In contrast to variational schemes, it does not assume conditional independence between the states and parameters. Generalised Filtering optimises the conditional density with respect to a free-energy bound on the model's log-evidence. This optimisation uses the generalised motion of hidden states and parameters, under the prior assumption that the motion of the parameters is small. We describe the scheme, present comparative evaluations with a fixed-form variational version, and conclude with an illustrative application to a nonlinear state-space model of brain imaging time-series.

  1. Advancement of safeguards inspection technology for CANDU nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jae Sung; Park, W. S.; Cha, H. R.; Ham, Y. S.; Lee, Y. G.; Kim, K. P.; Hong, Y. D

    1999-04-01

    The objectives of this project are to develop both inspection technology and safeguards instruments, related to CANDU safeguards inspection, through international cooperation, so that those outcomes are to be applied in field inspections of national safeguards. Furthermore, those could contribute to the improvement of verification correctness of IAEA inspections. Considering the level of national inspection technology, it looked not possible to perform national inspections without the joint use of containment and surveillance equipment conjunction with the IAEA. In this connection, basic studies for the successful implementation of national inspections was performed, optimal structure of safeguards inspection was attained, and advancement of safeguards inspection technology was forwarded. The successful implementation of this project contributed to both the improvement of inspection technology on CANDU reactors and the implementation of national inspection to be performed according to the legal framework. In addition, it would be an opportunity to improve the ability of negotiating in equal shares in relation to the IAEA on the occasion of discussing or negotiating the safeguards issues concerned. Now that the national safeguards technology for CANDU reactors was developed, the safeguards criteria, procedure and instruments as to the other item facilities and fabrication facilities should be developed for the perfection of national inspections. It would be desirable that the recommendations proposed and concreted in this study, so as to both cope with the strengthened international safeguards and detect the undeclared nuclear activities, could be applied to national safeguards scheme. (author)

  2. Safeguards and Security progress report, January--December 1989

    Energy Technology Data Exchange (ETDEWEB)

    Smith, D.B.; Jaramillo, G.R. (comps.)

    1990-11-01

    From January to December 1989, the Los Alamos Safeguards and Security Research and Development (R D) program carried out the activities described in the first four parts of this report: Science and Technology Base Development, Basic Systems Design, Onsite Test and Evaluation and Facility Support, and International Safeguards. For the most part, these activities were sponsored by the Department of Energy's Office of Safeguards and Security. Part 1 covers development of the basic technology essential to continuing improvements in the practice of safeguards and security. It includes our computer security R D and the activities of the DOE Center for Computer Security, which provides the basis for encouraging and disseminating this important technology. Part 2 treats activities aimed at developing methods for designing and evaluating safeguards systems, with special emphasis on the integration of the several subsystems into a real safeguards system. Part 3 describes efforts of direct assistance to the DOE and its contractors and includes consultation on materials control and accounting problems, development and demonstration of specialized techniques and instruments, and comprehensive participation in the design and demonstration of advanced safeguards systems. Part 3 also reports a series of training courses in various aspects of safeguards that makes the technology more accessible to those who must apply it. Finally, Part 4 covers international safeguards activities, including both support to the International Atomic Energy Agency and bilateral exchanges. Part 5 reports several safeguards-related activities that have sponsors other than the DOE/OSS. 87 refs., 52 figs.

  3. Advancement of safeguards inspection technology for CANDU nuclear power plants

    International Nuclear Information System (INIS)

    The objectives of this project are to develop both inspection technology and safeguards instruments, related to CANDU safeguards inspection, through international cooperation, so that those outcomes are to be applied in field inspections of national safeguards. Furthermore, those could contribute to the improvement of verification correctness of IAEA inspections. Considering the level of national inspection technology, it looked not possible to perform national inspections without the joint use of containment and surveillance equipment conjunction with the IAEA. In this connection, basic studies for the successful implementation of national inspections was performed, optimal structure of safeguards inspection was attained, and advancement of safeguards inspection technology was forwarded. The successful implementation of this project contributed to both the improvement of inspection technology on CANDU reactors and the implementation of national inspection to be performed according to the legal framework. In addition, it would be an opportunity to improve the ability of negotiating in equal shares in relation to the IAEA on the occasion of discussing or negotiating the safeguards issues concerned. Now that the national safeguards technology for CANDU reactors was developed, the safeguards criteria, procedure and instruments as to the other item facilities and fabrication facilities should be developed for the perfection of national inspections. It would be desirable that the recommendations proposed and concreted in this study, so as to both cope with the strengthened international safeguards and detect the undeclared nuclear activities, could be applied to national safeguards scheme. (author)

  4. Pebble bed modular reactor safeguards: developing new approaches and implementing safeguards by design

    Energy Technology Data Exchange (ETDEWEB)

    Beyer, Brian David [Los Alamos National Laboratory; Beddingfield, David H [Los Alamos National Laboratory; Durst, Philip [INL; Bean, Robert [INL

    2010-01-01

    The design of the Pebble Bed Modular Reactor (PBMR) does not fit or seem appropriate to the IAEA safeguards approach under the categories of light water reactor (LWR), on-load refueled reactor (OLR, i.e. CANDU), or Other (prismatic HTGR) because the fuel is in a bulk form, rather than discrete items. Because the nuclear fuel is a collection of nuclear material inserted in tennis-ball sized spheres containing structural and moderating material and a PBMR core will contain a bulk load on the order of 500,000 spheres, it could be classified as a 'Bulk-Fuel Reactor.' Hence, the IAEA should develop unique safeguards criteria. In a multi-lab DOE study, it was found that an optimized blend of: (i) developing techniques to verify the plutonium content in spent fuel pebbles, (ii) improving burn-up computer codes for PBMR spent fuel to provide better understanding of the core and spent fuel makeup, and (iii) utilizing bulk verification techniques for PBMR spent fuel storage bins should be combined with the historic IAEA and South African approaches of containment and surveillance to verify and maintain continuity of knowledge of PBMR fuel. For all of these techniques to work the design of the reactor will need to accommodate safeguards and material accountancy measures to a far greater extent than has thus far been the case. The implementation of Safeguards-by-Design as the PBMR design progresses provides an approach to meets these safeguards and accountancy needs.

  5. Next generation safeguards initiative (NGSI) program plan for safeguards by design

    Energy Technology Data Exchange (ETDEWEB)

    Demuth, Scott F [Los Alamos National Laboratory; Budlong - Sylvester, Kory [Los Alamos National Laboratory; Lockwood, Dunbar [DOE/NA-243

    2010-01-01

    Safeguards by Design (SBD) is defined as the incorporation of safeguards features early in the design phase of a new nuclear facility in order to avoid the need to redesign the facility at a later date, or retrofit the completed facility. Not only can SBD avoid the need for redesign or retrofit, but consideration of safeguards features early in the facility design effort can provide for a more efficient and effective safeguards design. A program has been initiated by the United States Department of Energy during the past several years to develop, demonstrate and institutionalization SBD. This plan has been developed in parallel with a similar effort at the IAEA while taking into account their achievements and future plans. The United States SBD program is focused on (1) identification of best practices that satisfy existing safeguards requirements, (2) identification of advanced concepts where best practices can be improved, and (3) institutionalizing SBD by gaining its acceptance as a global norm for the design of new nuclear facilities. SBD guidance documents are being prepared as an aid to industry for their design activities, to describe the relationship between requirements, best practices, and advanced concepts. SBD 'lessons learned' studies have been conducted to help identify the existing best practices and potential areas for improvement. Finally, acceptance as a global norm is being pursued by way of international workshops, engagement with industry and the IAEA, and setting an example by way of its use in new nuclear facilities in the United States.

  6. IAEA safeguards and non-proliferation

    International Nuclear Information System (INIS)

    An overview is given of the efforts to contain the nuclear weapons proliferation during half a century of man-controlled nuclear fission. An initial policy of denial did not work, a following period of cooperation needed a gradual strengthening of international assurances on the exclusively peaceful character of the flourishing use of nuclear techniques for power generation and of other applications. The focus of the nuclear weapon proliferation concern changed from the highly developed states to developing states. The Non-Proliferation Treaty laid the basis for a unique system of voluntarily accepted international inspections to verify the peaceful use of nuclear energy. The IAEA got the task to implement this 'Full Scope Safeguards' on all nuclear material and all nuclear activities in the non-nuclear weapon states. Thanks to the structure of the IAEA, in which both proponent and states with a critical attitude take part in the decision making process on the IAEA execution of its tasks, a balanced, and widely acceptable system emerged. International developments necessitated additional improvements of the non-proliferation system. The increase of strength of sub-national groups triggered international cooperation on physical protection, about a quarter of a century ago. More recently, it appeared that NPT states with assumed nuclear weapon ambitions operated in the margins between the interpretation of IAEA safeguards and the spirit and purpose of NPT. Improvements of the IAEA safeguards and a stronger cooperation between states, including the constraints which exporting states have imposed on nuclear supplies, strengthen the safeguards system. The important reductions in the two largest nuclear weapon arsenals lead, together with the delay in the fast breeder implementation, to large stockpiles of nuclear weapon usable materials. Also in this areas new internationally credible assurances have to be obtained, that these materials will never return to nuclear

  7. IAEA safeguards and non-proliferation

    Energy Technology Data Exchange (ETDEWEB)

    Harry, R.J.S.

    1995-02-01

    An overview is given of efforts to contain the nuclear weapons proliferation during half a century of man-controlled nuclear fission. An initial policy of denial did not work, a following period of cooperation needed a gradual strengthening of international assurances on the peaceful character of the flourishing use of nuclear techniques for power generation and of other applications. The focus of the nuclear weapon proliferation concern changed from the highly developed states to developing states. The Non-Proliferation Treaty laid the basis for a unique system of voluntarily accepted international inspections to verify the peaceful use of nuclear energy. The IAEA got the task to implement this `Full Scope Safeguards` on all nuclear material and all nuclear activities in the non-nuclear weapon states. Thanks to the structure of the IAEA, in which both proponent and states with a critical attitude take part in the decision making process on the IAEA execution of its tasks, a balanced, and widely acceptable system emerged. International developments necessitated additional improvements of the non-proliferation system. The increase of strength of sub-national groups triggered international cooperation on physical protection, about a quarter of a century ago. More recently, it appeared that NPT states with assumed nuclear weapon ambitions operated in the margins between the interpretation of IAEA safeguards and the spirit and purpose of NPT. Improvements of the IAEA safeguards and a stronger cooperation between states, including the constraints which exporting states have imposed on nuclear supplies, strengthen the safeguards system. The important reductions in the two largest nuclear weapon arsenals lead, together with the delay in the fast breeder implementation, to large stockpiles of nuclear weapon usable materials. Also in this areas new internationally credible assurances have to be obtained, that these materials will never return to nuclear weapon applications.

  8. Simulation of nuclear fuel reprocessing for safeguards

    International Nuclear Information System (INIS)

    For safeguarding the chemical process area of future reprocessing plants the near-real-time material accountancy (NRTMA) method might be applied. Experimental data are not yet available for testing the capability of the NRTMA method but can be simulated using a digital computer. This report describes the mathematical modeling of the Pu-bearing components of reprocessing plants and presents first results obtained by simulation models. (orig.)

  9. Strengthening IAEA Safeguards for Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Reid, Bruce D.; Anzelon, George A.; Budlong-Sylvester, Kory

    2016-09-28

    During their December 10-11, 2013, workshop in Grenoble France, which focused on the history and future of safeguarding research reactors, the United States, France and the United Kingdom (UK) agreed to conduct a joint study exploring ways to strengthen the IAEA’s safeguards approach for declared research reactors. This decision was prompted by concerns about: 1) historical cases of non-compliance involving misuse (including the use of non-nuclear materials for production of neutron generators for weapons) and diversion that were discovered, in many cases, long after the violations took place and as part of broader pattern of undeclared activities in half a dozen countries; 2) the fact that, under the Safeguards Criteria, the IAEA inspects some reactors (e.g., those with power levels under 25 MWt) less than once per year; 3) the long-standing precedent of States using heavy water research reactors (HWRR) to produce plutonium for weapons programs; 4) the use of HEU fuel in some research reactors; and 5) various technical characteristics common to some types of research reactors that could provide an opportunity for potential proliferators to misuse the facility or divert material with low probability of detection by the IAEA. In some research reactors, for example, such characteristics include rapid on-line refueling, and a core design with room for such a large number of assemblies or targets that it is difficult to detect diversion or undeclared irradiation. In addition, infrastructure associated with research reactors, such as hot cells, where plutonium could be separated, could pose a safeguards challenge because, in some cases, they are not declared (because they are not located in the facility or because nuclear materials are not foreseen to be processed inside) and may not be accessible to inspectors in States without an Additional Protocol in force.

  10. Science and Technology Challenges for International Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Mark Schanfein

    2009-07-01

    The science and technology challenges for international safeguards range from cutting edge physics needs to practical technology solutions for high volume data handling and analysis issues. This paper will take a narrow look at some of the predominant challenges, which include those at high throughput commercial facilities and those in the detection of undeclared facilities. It is hoped that by highlighting these areas it can encourage a concerted effort by scientific institutions and industry to provide robust cost-effective solutions.

  11. Strengthening IAEA Safeguards for Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Reid, Bruce D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Anzelon, George A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Budlong-Sylvester, Kory [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-09-01

    During their December 10-11, 2013, workshop in Grenoble France, which focused on the history and future of safeguarding research reactors, the United States, France and the United Kingdom (UK) agreed to conduct a joint study exploring ways to strengthen the IAEA’s safeguards approach for declared research reactors. This decision was prompted by concerns about: 1) historical cases of non-compliance involving misuse (including the use of non-nuclear materials for production of neutron generators for weapons) and diversion that were discovered, in many cases, long after the violations took place and as part of broader pattern of undeclared activities in half a dozen countries; 2) the fact that, under the Safeguards Criteria, the IAEA inspects some reactors (e.g., those with power levels under 25 MWt) less than once per year; 3) the long-standing precedent of States using heavy water research reactors (HWRR) to produce plutonium for weapons programs; 4) the use of HEU fuel in some research reactors; and 5) various technical characteristics common to some types of research reactors that could provide an opportunity for potential proliferators to misuse the facility or divert material with low probability of detection by the IAEA. In some research reactors, for example, such characteristics include rapid on-line refueling, and a core design with room for such a large number of assemblies or targets that it is difficult to detect diversion or undeclared irradiation. In addition, infrastructure associated with research reactors, such as hot cells, where plutonium could be separated, could pose a safeguards challenge because, in some cases, they are not declared (because they are not located in the facility or because nuclear materials are not foreseen to be processed inside) and may not be accessible to inspectors in States without an Additional Protocol in force.

  12. Croatian Support for Strengthening International Safeguards

    International Nuclear Information System (INIS)

    Nuclear science and technology has the potential to contribute to health and prosperity. However, it is also the basis for the development of nuclear weapons. The acceptance and implementation of IAEA safeguards therefore serve as important confidence building measures, through which a State can demonstrate, and other States can be assured, that nuclear energy is being used only for peaceful purpose. Practically, all countries around the world use nuclear techniques for a variety of peaceful purposes, including food and water security, energy, industrial application and human health. Only a few of these activities involve the type of nuclear material that could potentially be diverted to make nuclear weapons or other explosive devices. And here the safeguards are on duty. The safeguards system aims at detecting the diversion of nuclear material. In this paper will be presented international conventions and bilateral agreements in the field of nuclear safety as well as the Croatian cooperation with international organizations and associations in the nuclear area, such as Nuclear Supplier Group, Zangger Committee, Wassenaar Arrangement, Comprehensive Nuclear-Test- Ban treaty Organization, Euratom and civil expert groups of NATO. (author)

  13. Next Generation Germanium Systems for Safeguards Applications

    International Nuclear Information System (INIS)

    We are developing the latest generation of highly portable, mechanically cooled germanium systems for safeguard applications. In collaboration with our industrial partner, Ph.D.s Co, we have developed the Germanium Gamma Ray Imager (GeGI), an imager with a 2π field of view. This instrument has been thoroughly field tested in a wide range of environments and have performed reliably even in the harshest conditions. The imaging capability of GeGI complements existing safeguards techniques by allowing for the spatial detection, identification, and characterization of nuclear material. Additionally, imaging can be used in design information verification activities to address potential material diversions. Measurements conducted at the Paducah Gaseous Diffusion Plant highlight the advantages this instrument offers in the identification and localization of LEU, HEU and Pu holdup. GeGI has also been deployed to the Savannah River Site for the measurement of radioactive waste canisters, providing information valuable for waste characterization and inventory accountancy. Measuring 30 x 15 x 23 cm and weighing approximately 15 kg, this instrument is the first portable germanium-based imager. GeGI offers high reliability with the convenience of mechanical cooling, making this instrument ideal for the next generation of safeguards instrumentation. (author)

  14. Safety, Security and Safeguards (3S) Culture

    International Nuclear Information System (INIS)

    A meaningful discussion of Safety, Security, and Safeguards (3S) Culture requires a review of the concepts related to the culture of the three components. The concept of culture can be confusing, and so careful use of terminology is needed to enable a focused and constructive dialogue. To this end, this paper will use the concept of organizational culture as a backdrop for a broader discussion about how the three subcultures of safety, security and safeguards come together to enhance the mission of an organization. Since the accidents at Three Mile Island and Chernobyl, the nuclear industry has embraced the concept of safety culture. The work on safety culture has been used to develop programs and concepts in the culture of Material Protection, Control, and Accounting and Nuclear Security Culture. More recently, some work has been done on defining an International Safeguards Culture. Others have spoken about a 3S Culture, but there has been little rigorous consideration of the concept. This paper attempts to address 3S Culture, to begin to evaluate the merit of the concept, and to propose a definition. The paper is followed by the slides of the presentation. (authors)

  15. Review of the nuclear safeguards problem

    International Nuclear Information System (INIS)

    The issues surrounding nuclear safeguards are proliferation and terrorism. Protecting the nuclear fuel cycle against nuclear materials diversion has been the function of the NPT and the IAEA. However, because all nations have not signed the NPT and IAEA safeguarding inspections are not foolproof, the fuel cycle itself has been looked to as a possible way to alleviate concerns over proliferation. A civilian nuclear industry is not needed to produce weapon material, since research reactors can provide the necessary weapon-grade uranium or plutonium much cheaper and easier than commercial power reactors. Thus, altering the nuclear fuel cycle does not necessarily reduce the possibility of proliferation of nuclear weapons. Only strict enforcement of the NPT and of the safeguard guidelines of the IAEA can achieve nonproliferation. Changing the fuel cycle does not present terrorists from stealing highly radioactive material to be used for weapons or from sabotaging nuclear facilities. Policing a nuclear facility by using guards, alarms, barriers, and searching and screening of employees is the only way to protect against terrorism, but these actions raise questions regarding civil liberties

  16. Achievements to date in strengthened safeguards

    International Nuclear Information System (INIS)

    There is substantial progress in developing and implementing measures to strengthen the effectiveness and improve the efficiency of the Safeguards System. The measures comprise those to be implemented pursuant to the Agency's legal authority conferred by existing safeguards agreements as well as those to be implemented under the complementary legal authority conferred by Additional Protocols concluded on the basis of Document INFCIRC/540(Corrected). Activities on implementing measures under existing legal authority, particularly with respect to the evaluation of States' nuclear programmes, environmental sampling and the use of remote monitoring for safeguards purposes had been carried continuously ion the recent post. In 1998, additional protocols entered into force with four States (the Holy See, Jordan, New Zealand and Uzbekistan). Additional protocols with a further 27 States were approved by the Board and were awaiting ratification by the respective States. The additional protocol with Australia, which entered into force in December 1997, was being implemented following receipt of its Article 2 declaration. Agency consultations on concluding additional protocols take place with a number of States on a regular basis. As of 1 October 1999, Additional Protocols had been concluded and approved by the Board of Governors with a total of 45 States. Of these, Additional Protocols with 44 States had been signed and five had entered into force. (author)

  17. Safeguards First Principle Initiative (SFPI) Cost Model

    Energy Technology Data Exchange (ETDEWEB)

    Mary Alice Price

    2010-07-11

    The Nevada Test Site (NTS) began operating Material Control and Accountability (MC&A) under the Safeguards First Principle Initiative (SFPI), a risk-based and cost-effective program, in December 2006. The NTS SFPI Comprehensive Assessment of Safeguards Systems (COMPASS) Model is made up of specific elements (MC&A plan, graded safeguards, accounting systems, measurements, containment, surveillance, physical inventories, shipper/receiver differences, assessments/performance tests) and various sub-elements, which are each assigned effectiveness and contribution factors that when weighted and rated reflect the health of the MC&A program. The MC&A Cost Model, using an Excel workbook, calculates budget and/or actual costs using these same elements/sub-elements resulting in total costs and effectiveness costs per element/sub-element. These calculations allow management to identify how costs are distributed for each element/sub-element. The Cost Model, as part of the SFPI program review process, enables management to determine if spending is appropriate for each element/sub-element.

  18. Safeguards First Principle Initiative (SFPI) Cost Model

    International Nuclear Information System (INIS)

    The Nevada Test Site (NTS) began operating Material Control and Accountability (MC and A) under the Safeguards First Principle Initiative (SFPI), a risk-based and cost-effective program, in December 2006. The NTS SFPI Comprehensive Assessment of Safeguards Systems (COMPASS) Model is made up of specific elements (MC and A plan, graded safeguards, accounting systems, measurements, containment, surveillance, physical inventories, shipper/receiver differences, assessments/performance tests) and various sub-elements, which are each assigned effectiveness and contribution factors that when weighted and rated reflect the health of the MC and A program. The MC and A Cost Model, using an Excel workbook, calculates budget and/or actual costs using these same elements/sub-elements resulting in total costs and effectiveness costs per element/sub-element. These calculations allow management to identify how costs are distributed for each element/sub-element. The Cost Model, as part of the SFPI program review process, enables management to determine if spending is appropriate for each element/sub-element.

  19. Nuclear safeguards research and development program. Status report, January--April 1977

    Energy Technology Data Exchange (ETDEWEB)

    Sapir, J.L. (comp.)

    1977-06-01

    The status of the Nuclear Safeguards Research and Development program pursued by LASL Safeguards Groups Q-1, Q-2, Q-3, and Q-4 is presented . Topics covered include nondestructive assay technology development and applications, international safeguards, perimeter safeguards and surveillance, concepts and subsystems development (e.g., DYMAC program), integrated safeguards systems, training courses, and technology transfer.

  20. The state-level approach: moving beyond integrated safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Tape, James W [Los Alamos National Laboratory

    2008-01-01

    The concept of a State-Level Approach (SLA) for international safeguards planning, implementation, and evaluation was contained in the Conceptual Framework for Integrated Safeguards (IS) agreed in 2002. This paper describes briefly the key elements of the SLA, including State-level factors and high-level safeguards objectives, and considers different cases in which application of the SLA methodology could address safeguards for 'suspect' States, 'good' States, and Nuclear Weapons States hosting fuel cycle centers. The continued use and further development of the SLA to customize safeguards for each State, including for States already under IS, is seen as central to effective and efficient safeguards for an expanding nuclear world.

  1. Process monitoring for reprocessing plant safeguards: a summary review

    International Nuclear Information System (INIS)

    Process monitoring is a term typically associated with a detailed look at plant operating data to determine plant status. Process monitoring has been generally associated with operational control of plant processes. Recently, process monitoring has been given new attention for a possible role in international safeguards. International Safeguards Project Office (ISPO) Task C.59 has the goal to identify specific roles for process monitoring in international safeguards. As the preliminary effort associated with this task, a review of previous efforts in process monitoring for safeguards was conducted. Previous efforts mentioned concepts and a few specific applications. None were comprehensive in addressing all aspects of a process monitoring application for safeguards. This report summarizes the basic elements that must be developed in a comprehensive process monitoring application for safeguards. It then summarizes the significant efforts that have been documented in the literature with respect to the basic elements that were addressed

  2. Safeguards-by-Design: Early Integration of Physical Protection and Safeguardability into Design of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    T. Bjornard; R. Bean; S. DeMuth; P. Durst; M. Ehinger; M. Golay; D. Hebditch; J. Hockert; J. Morgan

    2009-09-01

    The application of a Safeguards-by-Design (SBD) process for new nuclear facilities has the potential to minimize proliferation and security risks as the use of nuclear energy expands worldwide. This paper defines a generic SBD process and its incorporation from early design phases into existing design / construction processes and develops a framework that can guide its institutionalization. SBD could be a basis for a new international norm and standard process for nuclear facility design. This work is part of the U.S. DOE’s Next Generation Safeguards Initiative (NGSI), and is jointly sponsored by the Offices of Non-proliferation and Nuclear Energy.

  3. Water Filter

    Science.gov (United States)

    1982-01-01

    A compact, lightweight electrolytic water sterilizer available through Ambassador Marketing, generates silver ions in concentrations of 50 to 100 parts per billion in water flow system. The silver ions serve as an effective bactericide/deodorizer. Tap water passes through filtering element of silver that has been chemically plated onto activated carbon. The silver inhibits bacterial growth and the activated carbon removes objectionable tastes and odors caused by addition of chlorine and other chemicals in municipal water supply. The three models available are a kitchen unit, a "Tourister" unit for portable use while traveling and a refrigerator unit that attaches to the ice cube water line. A filter will treat 5,000 to 10,000 gallons of water.

  4. Collection and Analysis of Open Source News for Information Awareness and Early Warning in Nuclear Safeguards

    International Nuclear Information System (INIS)

    Acquisition and analysis of open source information plays an increasingly important role in the IAEA’s move towards safeguards implementation based on all safeguards relevant information known about a State. The growing volume of open source information requires the development of technology and tools capable of effectively collecting relevant information, filtering out “noise”, organizing valuable information in a clear and accessible manner, and assessing its relevance. In this context, the IAEA’s Division of Information Management (SGIM) and the EC’s Joint Research Centre (JRC) are currently implementing a joint project to advance the effectiveness and efficiency of the IAEA’s workflow for open source information collection and analysis. The objective is to provide tools to support SGIM in the production of the SGIM Open Source Highlights, which is a daily news brief consisting of the most pertinent news stories relevant to safeguards and non-proliferation. The process involves the review and selection of hundreds of articles from a wide array of specifically selected sources. The joint activity exploits the JRC’s Europe Media Monitor (EMM) and NewsDesk applications: EMM automatically collects and analyses news articles from a pre-defined list of web sites, and NewsDesk allows an analyst to manually select the most relevant articles from the EMM stream for further processing. The paper discusses the IAEA’s workflow for the production of SGIM Open Source Highlights and describes the capabilities of EMM and NewsDesk. It then provides an overview of the joint activities since the project started in 2011, which were focused i) on setting up a separate EMM installation dedicated to the nuclear safeguards and security domain (Nuclear Security Media Monitor, NSMM) and ii) on evaluating the NSMM/NewsDesk for meeting the IAEA’s needs. Finally, it presents the current use NSMM/NewsDesk at the IAEA and proposes options for further integration with the

  5. A standard method for measuring benzene and formaldehyde emissions from candles in emission test chambers for human health risk assessment purposes.

    Science.gov (United States)

    Petry, Thomas; Cazelle, Elodie; Lloyd, Paul; Mascarenhas, Reuben; Stijntjes, Gerard

    2013-07-01

    Burning candles release a number of volatile or semi-volatile organic compounds (VOC; SVOC) and particulate matters into indoor air. Publicly available candle emission studies vary in protocols and factors known to have a great influence on combustion processes, making it difficult to determine potential implications of candle emissions for human health. The main objective of this investigation was to establish and standardize as far as possible a candle VOC emission testing protocol in small- to mid-scale test chambers on the basis of existing standards as well as to verify its suitability for human health risk assessment purposes. Two pilot studies were conducted to define the boundaries of permissible variations in chamber parameters without significantly impacting the quality of the candle burn. A four-centre ring trial assessed the standardised protocol. The ring trial revealed that when the laboratories were able to control the chamber parameters within the defined boundaries, reproducible formaldehyde and benzene emissions, considered as VOC markers, are determined. It was therefore concluded that the protocol developed in this investigation is suitable for generating candle VOC emission data for human health risk assessment purposes. PMID:23695106

  6. Application and research status of vegetable oil in candle%植物油在蜡烛中的应用及研究进展

    Institute of Scientific and Technical Information of China (English)

    赵雪丹; 毕艳兰; 张虹; 陈丽丽; 肖宇峰; 徐学兵

    2014-01-01

    植物油作为一种可替代石蜡的绿色环保、可再生的新兴蜡材,其在环境保护及维护人体健康方面具有重要意义。概述了植物油在蜡烛中应用的优势及存在的问题,以油脂结晶相关理论为基础论述了影响植物油基蜡烛外观品质的因素及改善方法,对比了植物油基与石蜡型蜡烛的燃烧性能,并展望了植物油在蜡烛行业中的应用前景。%As a renewable replacement for paraffin, vegetable oil plays an important role in environmental protection and human health. The advantages and disadvantages of application of vegetable oil in candle were summarized. Based on the related theory of oil crystallization, the major impact factors of appear-ance of vegetable oil-based candle and the methods to improve candle quality were discussed, the com-bustion properties of vegetable oil-based candle and paraffin-based candle were compared, and the ap-plication of vegetable oil in candle was prospected.

  7. Modeling and Simulation for Safeguards and Nonproliferation Workshop

    Energy Technology Data Exchange (ETDEWEB)

    Gilligan, Kimberly V. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Kirk, Bernadette Lugue [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-01-01

    The Modeling and Simulation for Safeguards and Nonproliferation Workshop was held December 15–18, 2014, at Oak Ridge National Laboratory. This workshop was made possible by the Next Generation Safeguards Initiative Human Capital Development (NGSI HCD) Program. The idea of the workshop was to move beyond the tried-and-true boot camp training of nonproliferation concepts to spend several days on the unique perspective of applying modeling and simulation (M&S) solutions to safeguards challenges.

  8. Summary of achievements in safeguards implementation at the Nukem plant

    International Nuclear Information System (INIS)

    This document reviews the achievements in safeguards development studies and in safeguards implementation in a highly enriched uranium fuel fabrication plant. The study was performed at the Nukem plant of Wolfgang-Hanau (Federal Republic of Germany). The report is the result of the combined efforts of the Joint Research Centre (Ispra Establishment, Safeguards and fissile material management project) and the Safegards Directorate of Euratom, with the continuous collaboration of the operator of the plant

  9. 负压区的存在对刚性陶瓷过滤器脉冲反吹性能的影响%EFFECT OF NEGATIVE PRESSURE REGION ON PULSE-JET CLEANING PERFORMANCE OF RIGID CERAMIC FILTERS

    Institute of Scientific and Technical Information of China (English)

    姬忠礼; 郭建光

    2000-01-01

    利用压电式压力传感器测定了陶瓷过滤器在脉冲反吹过程中滤管内动态压力的变化规律,表明在脉冲反吹快要结束和正常过滤尚未开始的过渡过程中,滤管内存在严重的负压区。利用单个颗粒轨道模型分析了部分已被吹离滤管表面的小颗粒在负压区的作用下会重新返回到滤管壁,从而证实了负压区是影响刚性陶瓷过滤器稳定运行的重要原因。%In a ceramic filter experimental set-up with three filter candles,the dynamic pressures atthe inner wall of one filter candle during pulse-jet cleaning aremeasured by using resize-electric pressure transducer. The experimentalresults show that the dynamic pressure in wholepulse-jet cleaning process consists of two parts. One is the positivepressure in the filter candlegreater than the pressure outside the filter candle whichcorresponds to the outward radial fluidflow to break up and dislodge the dust cake on the surfaceof the filter tube. The other is anegative pressure region which is responsible for inward radialflow while the pulse-jet is closed.The influences of reservoir pressure on thedynamic pressure are discussed.The calculation results of particle motion indicate that negativepressure region cause a fractionof particles removed re-deposit on the candle surface. Especiallyfiner particles is more easierlyre-deposited on the surface to form thin and dense layer on thefilter candle and to increasegradually the residual pressure drop across the candle. It isconcluded that negative pressureregion may have important effects on the long-term stable operation of thefilter unit.

  10. Safeguards Culture: Analogies from Safety Culture and Security Culture

    International Nuclear Information System (INIS)

    The terminology of 'safeguards culture' has been used loosely by safeguards experts as an essential element for establishing an organizational environment of stakeholders for the effective and efficient implementation of international safeguards. However, unlike the other two triplet brothers/ sisters of 3S's (Safety, Security, Safeguards), there is no formally established definition of safeguards culture. In the case of safety culture, INSAG (the International Nuclear Safety Advisory Group) has extensively dealt with its concept, elaborating its definition and key characteristics, and published its report, INSAG-4, as the IAEA Safety Series 75. On the other hand, security culture has also been defined by AdSec (the Advisory Group on Nuclear Security). In this paper, a provisional definition of safeguards culture is made on the analogies of safety culture and security culture, and an effort is made to describe essential elements of safeguards culture. It is proposed for SAGSI (the Standing Advisory Group on Safeguards Implementation) to formally consider the definition of safeguards culture and its characteristics. The paper is followed by the slides of the presentation. (author)

  11. An American Academy for Training Safeguards Inspectors - An Idea Revisited

    International Nuclear Information System (INIS)

    In 2009, we presented the idea of an American academy for training safeguards inspectors for the International Atomic Energy Agency (IAEA), due to the declining percentage of Americans in that international organization. In this paper we assert that there is still a compelling need for this academy. While the American Safeguards Academy would be useful in preparing and pre-training American inspectors for the IAEA, it would also be useful for preparing Americans for domestic safeguards duties in the U.S. Department of Energy (DOE), U.S. DOE National Laboratories, and the U.S. Nuclear Regulatory Commission (NRC). It is envisioned that such an academy would train graduate and post-graduate university students, DOE National Laboratory interns, and nuclear safeguards professionals in the modern equipment, safeguards measures, and approaches currently used by the IAEA. It is also envisioned that the Academy would involve the domestic nuclear industry, which could provide use of commercial nuclear facilities for tours and demonstrations of the safeguards tools and methods in actual nuclear facilities. This would be in support of the U.S. DOE National Nuclear Security Administration's Next Generation Safeguards Initiative (NGSI). This training would also help American nuclear safeguards and non-proliferation professionals better understand the potential limitations of the current tools used by the IAEA and give them a foundation from which to consider even more effective and efficient safeguards measures and approaches.

  12. Comprehensive safeguards evaluation methods and societal risk analysis

    International Nuclear Information System (INIS)

    Essential capabilities of an integrated evaluation methodology for analyzing safeguards systems are discussed. Such a methodology must be conceptually meaningful, technically defensible, discriminating and consistent. A decompostion of safeguards systems by function is mentioned as a possible starting point for methodology development. The application of a societal risk equation to safeguards systems analysis is addressed. Conceptual problems with this approach are discussed. Technical difficulties in applying this equation to safeguards systems are illustrated through the use of confidence intervals, information content, hypothesis testing and ranking and selection procedures

  13. Methodology and preliminary models for analyzing nuclear-safeguards decisions

    International Nuclear Information System (INIS)

    This report describes a general analytical tool designed with Lawrence Livermore Laboratory to assist the Nuclear Regulatory Commission in making nuclear safeguards decisions. The approach is based on decision analysis - a quantitative procedure for making decisions under uncertain conditions. The report: describes illustrative models that quantify the probability and consequences of diverted special nuclear material and the costs of safeguarding the material; demonstrates a methodology for using this information to set safeguards regulations (safeguards criteria); and summarizes insights gained in a very preliminary assessment of a hypothetical reprocessing plant

  14. Technology transfer significance of the International Safeguards Project Office

    Energy Technology Data Exchange (ETDEWEB)

    Marcuse, W.; Wallgura, A.J.

    1988-01-01

    The safeguards implemented by the International Atomic Energy Agency (IAEA) are of major importance to the non-proliferation objectives of the United States of America and other nations of the world. Assurance of safeguards effectiveness is mandatory to continued peaceful use of nuclear power. To enhance the ability of the IAEA to apply safeguards effectively, and to ensure that the IAEA does not lack technical assistance in critical areas, the U.S. Congress has made available a special authorization for a Program for Technical Assistance to IAEA Safeguards (POTAS). In expediting the program full use is made of existing DOE laboratory resources.

  15. Paying tribute to 25 years of safeguards leadership

    International Nuclear Information System (INIS)

    After phases of intensive development in the 1970s and consolidation in the 1980s, the IAEA's international safeguards system is now in a phase of transition. The 1990s look to be a time when verification activities are further expanded in response to global developments and challenges in the field of nuclear non-proliferation. How far have safeguards come, and where are they headed? This article offers some thoughts and perspectives on the main challenges and opportunities facing IAEA safeguards, in the context of some recent developments and the overall evolution of the safeguards system

  16. Development of the strengthened safeguards system and the Additional Protocol

    International Nuclear Information System (INIS)

    For the past 30 years, the IAEA's safeguards system has contributed to the international non-proliferation regime by providing, inter alia, assurances regarding the peaceful uses of declared nuclear material. However, the discovery of a clandestine nuclear weapons program in Iraq in 1991 drew world-wide attention to the need to strengthen the system to address the absence of undeclared nuclear material and activities. Efforts to strengthen the IAEA's safeguards system began in 1991 and culminated in 1997 when the IAEA's Board of Governors approved a Model Protocol Additional to IAEA Safeguards Agreements which greatly expands the legal basis and scope of IAEA safeguards. Within this strengthened system it is expected that the IAEA be able to provide assurance not only of the absence of diversion of declared nuclear material but also on the absence of undeclared nuclear material and activities. This is to be done within a safeguards system that uses an optimal combination of all safeguards measures available, thereby achieving maximum effectiveness and efficiency within the available resources. The paper summarizes the evolution of the safeguards system, describes strengthened safeguards, reports on the status of implementing the strengthening measures, and outlines plans for integrating all available safeguards measures. (author)

  17. Surface brightness, standard candles and q/0/. [universe deceleration parameter determination by redshift-magnitude relation of extragalactic sources

    Science.gov (United States)

    Petrosian, V.

    1977-01-01

    The most direct way to determine the deceleration parameter, q(0), of the universe is through the study of the redshift-magnitude relation of extragalactic sources. Progress has been slow because the necessary sources for this study must be standard candles, which have identical absolute total luminosity (balometric or monochromatic). The present paper shows, first of all, that, although necessary, this is not a sufficient condition for nonpoint-like (or resolved) sources. A modification of the redshift-magnitude relation is then described for a certain class of nonstandard candles using measurements of isophotal surface brightness. It is noted that such measurements can be used to standardize the central surface brightness of galaxies, but the standardization of the scale parameter remains beyond observations.

  18. The impact of candle burning during All Saints' Day ceremonies on ambient alkyl-substituted benzene concentrations.

    Science.gov (United States)

    Olszowski, Tomasz; Kłos, Andrzej

    2013-11-01

    Research findings concerning benzene, toluene, ethylobenzene, meta-, para- and ortho-xylene as well as styrene (BTEXS) emission at public cemeteries during All Saints' Day are presented here. Tests were carried out at town-located cemeteries in Opole and Grodków (southern Poland) and, as a benchmark, at the centres of those same towns. The purpose of the study was to estimate BTEXS emissions caused by the candle burning and, equally important to examine, whether emissions generated by the tested sources were similar to the BTEXS emissions generated by road transport. During the festive period, significant increases in benzene concentrations, by 200 % and 144 %, were noted at the cemeteries in Opole and Grodków, as well as in toluene, by 366 % and 342 %, respectively. Styrene concentrations also increased. It was demonstrated that the ratio of toluene to benzene concentrations from emissions caused by the burning candles are comparable to the ratio established for transportation emissions. PMID:24052143

  19. “晨举脂烛”解诂%Gloss and Emendation on“Holding Candles at Dawn”

    Institute of Scientific and Technical Information of China (English)

    李朝虹

    2014-01-01

    描述武王克商的“晨举脂烛”一语多次出现在典籍中,而现代辞书对“晨”的解释基本统一为日出前后天色已明的一段时间,此时仍“举脂烛”作战实在令人费解。经过考证,“晨”在古汉语中的时段是凌晨3-5点,天仍未亮,因此才会出现“晨举脂烛”作战一说。%The phrase“holding candles at dawn” appeared many times in the ancient books when describing King Wu’s fights with King Shang .However ,in different modern dictionaries and works ,“dawn” is always explained as the time around sunrise when the sky is already wide bright .It is strange to “hold candles to fight enemy at the sunrise” .By analyzing historical documents ,it is found that the time of “dawn” refers to the early morning around 3-5 o’clock .Thus ,“holding candles at daw n” holds w ater .

  20. Laboratory Testing of the Boundary Layer Momentum Transfer Rotational Filter Systems, NETL-Innovatech, Inc., CRADA 98-F026, Final Report

    Energy Technology Data Exchange (ETDEWEB)

    National Energy Technology Laboratory

    2000-08-22

    A patented dynamic mechanical filter developed by InnovaTech was previously shown to remove fine particulate matter from industrial process gas streams at ambient temperatures and pressures. An all-metal, high-temperature version of this novel media-less filter was fabricated under this Cooperative Research and Development Agreement (CRADA) with DOE/NETL-Morgantown for hot gas testing of the device. The technology is entirely different in both concept and design from conventional vortex separators, cyclones, or porous media filters. This new filtration concept is capable of separating heavy loading of fine particles without blinding, fouling or bridging, and would require minimal operational costs over its anticipated multi-year service life. The all-metal filter design eliminates thermal stress cracking and premature failure prevalent in conventional porous ceramic filters. In contrast, conventional porous media filters (i.e., ceramic cross-flow or candles) easily foul, require periodic cleaning (typically backpulsing), frequent replacement and subsequent disposal.

  1. Laboratory Testing of the Boundary Layer Momentum Transfer Rotational Filter Systems, NETL-Innovatech, Inc., CRADA 98-F026, Final Report; FINAL

    International Nuclear Information System (INIS)

    A patented dynamic mechanical filter developed by InnovaTech was previously shown to remove fine particulate matter from industrial process gas streams at ambient temperatures and pressures. An all-metal, high-temperature version of this novel media-less filter was fabricated under this Cooperative Research and Development Agreement (CRADA) with DOE/NETL-Morgantown for hot gas testing of the device. The technology is entirely different in both concept and design from conventional vortex separators, cyclones, or porous media filters. This new filtration concept is capable of separating heavy loading of fine particles without blinding, fouling or bridging, and would require minimal operational costs over its anticipated multi-year service life. The all-metal filter design eliminates thermal stress cracking and premature failure prevalent in conventional porous ceramic filters. In contrast, conventional porous media filters (i.e., ceramic cross-flow or candles) easily foul, require periodic cleaning (typically backpulsing), frequent replacement and subsequent disposal

  2. Nuclear Resonance Fluorescence for Safeguards Applications

    Energy Technology Data Exchange (ETDEWEB)

    Ludewigt, Bernhard A; Quiter, Brian J; Ambers, Scott D

    2011-02-04

    In nuclear resonance fluorescence (NRF) measurements, resonances are excited by an external photon beam leading to the emission of {gamma} rays with specific energies that are characteristic of the emitting isotope. The promise of NRF as a non-destructive analysis technique (NDA) in safeguards applications lies in its potential to directly quantify a specific isotope in an assay target without the need for unfolding the combined responses of several fissile isotopes as often required by other NDA methods. The use of NRF for detection of sensitive nuclear materials and other contraband has been researched in the past. In the safeguards applications considered here one has to go beyond mere detection and precisely quantify the isotopic content, a challenge that is discussed throughout this report. Basic NRF measurement methods, instrumentation, and the analytical calculation of NRF signal strengths are described in Section 2. Well understood modeling and simulation tools are needed for assessing the potential of NRF for safeguards and for designing measurement systems. All our simulations were performed with the radiation transport code MCNPX, a code that is widely used in the safeguards community. Our initial studies showed that MCNPX grossly underestimated the elastically scattered background at backwards angles due to an incorrect treatment of Rayleigh scattering. While new, corrected calculations based on ENDF form factors showed much better agreement with experimental data for the elastic scattering of photons on an uranium target, the elastic backscatter is still not rigorously treated. Photonuclear scattering processes (nuclear Thomson, Delbruck and Giant Dipole Resonance scattering), which are expected to play an important role at higher energies, are not yet included. These missing elastic scattering contributions were studied and their importance evaluated evaluated against data found in the literature as discussed in Section 3. A transmission experiment

  3. Nuclear Resonance Fluorescence for Safeguards Applications

    International Nuclear Information System (INIS)

    In nuclear resonance fluorescence (NRF) measurements, resonances are excited by an external photon beam leading to the emission of γ rays with specific energies that are characteristic of the emitting isotope. The promise of NRF as a non-destructive analysis technique (NDA) in safeguards applications lies in its potential to directly quantify a specific isotope in an assay target without the need for unfolding the combined responses of several fissile isotopes as often required by other NDA methods. The use of NRF for detection of sensitive nuclear materials and other contraband has been researched in the past. In the safeguards applications considered here one has to go beyond mere detection and precisely quantify the isotopic content, a challenge that is discussed throughout this report. Basic NRF measurement methods, instrumentation, and the analytical calculation of NRF signal strengths are described in Section 2. Well understood modeling and simulation tools are needed for assessing the potential of NRF for safeguards and for designing measurement systems. All our simulations were performed with the radiation transport code MCNPX, a code that is widely used in the safeguards community. Our initial studies showed that MCNPX grossly underestimated the elastically scattered background at backwards angles due to an incorrect treatment of Rayleigh scattering. While new, corrected calculations based on ENDF form factors showed much better agreement with experimental data for the elastic scattering of photons on an uranium target, the elastic backscatter is still not rigorously treated. Photonuclear scattering processes (nuclear Thomson, Delbruck and Giant Dipole Resonance scattering), which are expected to play an important role at higher energies, are not yet included. These missing elastic scattering contributions were studied and their importance evaluated evaluated against data found in the literature as discussed in Section 3. A transmission experiment was

  4. 7 CFR 4290.506 - Safeguarding the RBIC's assets/Internal controls.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 15 2010-01-01 2010-01-01 false Safeguarding the RBIC's assets/Internal controls... Safeguarding the RBIC's assets/Internal controls. You must adopt a plan to safeguard your assets and monitor... your control procedures....

  5. Secret Objective Standoff: International Safeguards Educational Exercise

    Energy Technology Data Exchange (ETDEWEB)

    Okowita, Samantha L [ORNL

    2014-01-01

    The International Safeguards Regime, being so multi-faceted, can be overwhelming to those first introduced to its many components. The organizers and lecturers of workshops and courses on nonproliferation often provide a series of independent lectures and must somehow demonstrate the cohesive and effective nature of the system. An exercise titled The Secret Objective Standoff was developed to complement lectures with hands-on learning to assist participants in bringing all the many components (IAEA agreements, export controls, treaty obligations, international diplomacy, etc.) of the International Safeguards Regime together. This exercise divides participants into teams that are assigned the role of either a country or the IAEA and asks that they fully immerse themselves in their roles. The teams are then randomly assigned three unique and secret objectives that are intended to represent realistic and current geopolitical scenarios. Through construction, trading, or hoarding of four resources (experts, technology, money, and uranium), the teams have a finite number of turns to accomplish their objectives. Each turn has three phases random dispersal of resources, a timed discussion where teams can coordinate and strategize with others, and an action phase. During the action phase, teams inform the moderator individually and secretly what they will be doing that turn. The exercise has been tested twice with Oak Ridge National Laboratory personnel, and has been conducted with outside participants twice, in each case the experience was well received by both participants and instructors. This exercise provides instructors the ability to modify the exercise before or during game play to best fit their educational goals. By offering a range of experiences, from an in-depth look at specific components to a generalized overview, this exercise is an effective tool in helping participants achieve a full understanding the International Safeguards Regime.

  6. Development of Nuclear Material Accounting and Safeguards Technology

    International Nuclear Information System (INIS)

    This project is aimed at the development of nuclear material accounting and safeguards technology. Nuclear material accountancy technology for an each unit process and nuclear characteristic analysis technology to demonstrate the safeguards technology for a pyroprocessing facility have been developed during the first phase of the project. A study for analyzing the safeguardability of pyroprocessing facility and preliminary evaluation has also been carried out. The safeguards technology system for electro-reduction process has been established to develop the unit process nuclear material accountancy technology through nuclear material accounting in ACPF and performance test of surveillance equipment using spent fuels and neutron source. Nuclear material accountancy measure for electro-refining process where various kinds of nuclear materials are generated compared to electro-reduction process has been constructed, and its performance test has been conducted as well. A Gamma/neutron integrated system has been developed as a nuclear characteristic analysis technology for pyroprocess nuclear material, the possibility of Pu and U measurement has been analyzed using FRAM, and fundamental experiment has been performed to examine whether LIBS technology is applicable to nuclear material accountancy of pyroprocess. A preliminary concept design of safeguards system for pyroprocessing facility and basic design of computer code for analyzing the safeguardability have been carried out to perform the safeguardability analysis and preliminary evaluation for pyroprocessing facility, and a study for analyzing the safeguardability of KAPF which has scale of 100 MT-HM/year has been conducted in collaboration with LANL. Also, an IAEA Member State Support Program for establishing safeguards approach technology for pyroprocessing facility ('Support for Development for a Safeguards Approach for a Pyroprocessing Plant') has been conducting in cooperation with KINAC. It is expected that

  7. Safeguards Implementation Practices Guide on Facilitating IAEA Verification Activities

    International Nuclear Information System (INIS)

    The IAEA implements safeguards pursuant to agreements concluded with States. It is in the interests of both States and the IAEA to cooperate to facilitate the practical implementation of safeguards. Such cooperation is explicitly required under all types of safeguards agreement. Effective cooperation depends upon States and the IAEA sharing a common understanding of their respective rights and obligations. To address this, in 2012 the IAEA published Services Series 21, Guidance for States Implementing Comprehensive Safeguards Agreements and Additional Protocols, which aimed at enhancing understanding of the safeguards obligations of both States and the IAEA and at improving their cooperation in safeguards implementation. States may establish different processes and procedures at the national level, and set up different systems as required to meet their safeguards obligations. Indeed, a variety of approaches are to be expected, owing to such differences as the size and complexity of States’ nuclear programmes and their regulatory framework. The purpose of this Safeguards Implementation Practices (SIP) Guide is to share the experiences and good practices as well as the lessons learned by both States and the IAEA, acquired over the many decades of safeguards implementation. The information contained in the SIP Guides is provided for explanatory purposes and use of the Guides is not mandatory. The descriptions in the SIP Guides have no legal status and are not intended to add to, subtract from, amend or derogate from, in any way, the rights and obligations of the IAEA and the States set forth in The Structure and Content of Agreements between the Agency and States Required in Connection with the Treaty on the Non-Proliferation of Nuclear Weapons (issued as INFCIRC/153 (Corrected)) and Model Protocol Additional to the Agreement(s) between State(s) and the International Atomic Energy Agency for the Application of Safeguards (issued as INFCIRC/540 (Corrected)). This SIP

  8. Past, Present and Future of Safeguards in Lithuania

    Energy Technology Data Exchange (ETDEWEB)

    Davainis, Marius [State Nuclear Power Safety Inspectorate (VATESI), Vilnius (Lithuania)

    2003-05-01

    Changing Safeguards climate has been a phenomenon for already ten years in Lithuania. Since the Agreement between the Government of the Republic of Lithuania and the International Atomic Energy Agency for the Application of Safeguards in connection with the Treaty on the Non-proliferation of Nuclear Weapons was signed in 1992, two distinctive periods of five years could be discerned. Safeguards was a new matter in Lithuania back in 1992 and its perception was not a one day work. For instance, development of the national system of accounting for and control of nuclear material took years. Safeguards implementation in Lithuania was not a simple and easy task for the IAEA either. The Ignalina Nuclear Power Plant inherited by Lithuania from the Soviet Union brought its particularity, as there was no precedent experience in safeguarding the RBMK type reactors. Subsidiary Arrangements to the Safeguards Agreement and the national regulation for nuclear material accounting and control came into force in 1997. That year could be considered as the end of the first five- year period, which could be called an initial stage of Safeguards application in Lithuania. In March 1998 Lithuania signed the Additional Protocol to its Safeguards Agreement. After two years it was ratified and came into force on the 5th of July 2000. That was a certain change and a new stage of Safeguards application in Lithuania. The year 2000 was also the time when the EURATOM system appeared on the horizon. The 1st of January 2004 is the most likely date of accession of Lithuania to the European Union and it can be said that Safeguards in Lithuania is heading to the next generation. This paper is aimed to review developments, which took place and the experience gained through the ten years of Safeguards application in Lithuania and also to present some considerations about the approaching changes.

  9. The future of IAEA safeguards: challenges and responses

    Energy Technology Data Exchange (ETDEWEB)

    Pilat, Joseph F [Los Alamos National Laboratory; Budlong - Sylvester, Kory W [Los Alamos National Laboratory

    2011-01-01

    For nearly two decades, the International Atomic Energy Agency (lAEA) has been transforming its safeguards system to address the challenges posed by undeclared nuclear programs, the associated revelation of an extensive non-State nuclear procurement network and other issues, including past limits to its verification mandate and the burden of noncompliance issues. Implementing the new measures, including those in the Additional Protocol, and integrating new and old safeguards measures, remains a work in progress. Implementation is complicated by factors including the limited teclmological tools that are available to address such issues as safeguarding bulk handling facilities, detection of undeclared facilities/activities, especially related to enrichment, etc. As this process continues, new challenges are arising, including the demands of expanding nuclear power production worldwide, so-called safeguards by design for a new generation of facilities, the possible IAEA role in a fissile material cutoff treaty and other elements of the arms control and disarmament agenda, the possible role in 'rollback' cases, etc. There is no doubt safeguards will need to evolve in the future, as they have over the last decades. In order for the evolutionary path to proceed, there will inter alia be a need to identify technological gaps, especially with respect to undeclared facilities, and ensure they are filled by adapting old safeguards technologies, by developing and introducing new and novel safeguards teclmologies and/or by developing new procedures and protocols. Safeguards will also need to respond to anticipated emerging threats and to future, unanticipated threats. This will require strategic planning and cooperation among Member States and with the Agency. This paper will address challenges to IAEA safeguards and the technological possibilities and R&D strategies needed to meet those challenges in the context of the forty-year evolution of safeguards, including

  10. Digital filters

    CERN Document Server

    Hamming, Richard W

    1997-01-01

    Digital signals occur in an increasing number of applications: in telephone communications; in radio, television, and stereo sound systems; and in spacecraft transmissions, to name just a few. This introductory text examines digital filtering, the processes of smoothing, predicting, differentiating, integrating, and separating signals, as well as the removal of noise from a signal. The processes bear particular relevance to computer applications, one of the focuses of this book.Readers will find Hamming's analysis accessible and engaging, in recognition of the fact that many people with the s

  11. The organisation of interagency training to safeguard children in England: a case study using realistic evaluation

    OpenAIRE

    Patsios, Demi; Carpenter, John

    2010-01-01

    Background: Joint training for interagency working is carried out by Local Safeguarding Children Boards in England to promote effective local working to safeguard and promote the welfare of children.Purpose: This paper reports on the findings of the outputs and outcomes of interagency training to safeguard children in eight Local Safeguarding Children Boards.Methods: A review of Local Safeguarding Children Board documentation, observations of Local Safeguarding Children Board training sub-gro...

  12. Systems Analysis of Safeguards Effectiveness in a Uranium Conversion Facility

    Energy Technology Data Exchange (ETDEWEB)

    Elayat, H A; Lambert, H; O' Connell, W J

    2004-06-16

    The U.S. Department of Energy (DOE) is interested in developing tools and methods for potential U.S. use in designing and evaluating safeguards systems. For this goal several DOE National Laboratories are defining the characteristics of typical facilities of several size scales, and the safeguards measures and instrumentation that could be applied. Lawrence Livermore National Laboratory is providing systems modeling and analysis of facility and safeguards operations, diversion path generation, and safeguards system effectiveness. The constituent elements of diversion scenarios are structured using directed graphs (digraphs) and fault trees. Safeguards indicator probabilities are based on sampling statistics and/or measurement accuracies. Scenarios are ranked based on value and quantity of material removed and the estimated probability of non-detection. Significant scenarios, especially those involving timeliness or randomly varying order of events, are transferred to simulation analysis. Simulations show the range of conditions encountered by the safeguards measurements and inspections, e.g., the quantities of intermediate materials in temporary storage and the time sequencing of material flow. Given a diversion campaign, simulations show how much the range of the same parameters observed by the safeguards system can differ from the base-case range. The combination of digraphs, fault trees, statistics and simulation constitute a method for evaluation of the estimated benefit of alternate or additional safeguards equipment or features. A generic example illustrates the method.

  13. 42 CFR 438.58 - Conflict of interest safeguards.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 4 2010-10-01 2010-10-01 false Conflict of interest safeguards. 438.58 Section 438... (CONTINUED) MEDICAL ASSISTANCE PROGRAMS MANAGED CARE State Responsibilities § 438.58 Conflict of interest... safeguards against conflict of interest on the part of State and local officers and employees and agents...

  14. Safeguarding and Protecting Children in Maternity Services: Implications for Practice

    Science.gov (United States)

    Lazenbatt, Anne; Greer, Jean

    2009-01-01

    This article debates the issues involved in safeguarding and protecting children in maternity services and offers implications for professional practice. Midwives and other staff who work as members of the maternity team have a safeguarding role to play in the identification of babies and children who have been abused, or are at risk of abuse, and…

  15. Safeguards and security status report, August 1981-January 1982

    Energy Technology Data Exchange (ETDEWEB)

    Shipley, J.P. (comp.)

    1982-09-01

    From August 1981 through January 1982, the Los Alamos Safeguards and Security Program was involved in many activities that are described in the four parts of this report: Nuclear Facility Safeguards Support, Security Development and Support, Safeguards Technology Development, and International Support. Part 1 covers those efforts of direct assistance to the Department of Energy and the Nuclear Regulatory Commission licensee facilities. This assistance varies from consultation on materials accounting problems, through development of specialized techniques and devices, to comprehensive participation in the design and implementation of advanced safeguards systems. In addition, a series of training courses in various aspects of safeguards helps make the technology more accessible to those who must apply it. Part 2 concerns a relatively new set of activities at Los Alamos aimed at the security of information and computer systems. The focus this period has been on furthering the development of the Computer Security Center, which provides the basis for encouraging and disseminating the emerging technology. Part 3 describes the development efforts that are essential to continued improvements in the practice of safeguards. Although these projects are properly classified as developmental, in every case they are directed ultimately at recognized problems that commonly occur in operating facilities. Finally, Part 4 covers international safeguards activities, including both support to the International Atomic Energy Agency and bilateral exchanges. In addition, enrichment plant safeguards, especially those concerning the Gaseous Centrifuge Enrichment Plant, required a significant portion of our resources. These efforts are beginning to provide substantial returns on our investment in technology transfer.

  16. Safeguards and security status report, August 1981-January 1982

    International Nuclear Information System (INIS)

    From August 1981 through January 1982, the Los Alamos Safeguards and Security Program was involved in many activities that are described in the four parts of this report: Nuclear Facility Safeguards Support, Security Development and Support, Safeguards Technology Development, and International Support. Part 1 covers those efforts of direct assistance to the Department of Energy and the Nuclear Regulatory Commission licensee facilities. This assistance varies from consultation on materials accounting problems, through development of specialized techniques and devices, to comprehensive participation in the design and implementation of advanced safeguards systems. In addition, a series of training courses in various aspects of safeguards helps make the technology more accessible to those who must apply it. Part 2 concerns a relatively new set of activities at Los Alamos aimed at the security of information and computer systems. The focus this period has been on furthering the development of the Computer Security Center, which provides the basis for encouraging and disseminating the emerging technology. Part 3 describes the development efforts that are essential to continued improvements in the practice of safeguards. Although these projects are properly classified as developmental, in every case they are directed ultimately at recognized problems that commonly occur in operating facilities. Finally, Part 4 covers international safeguards activities, including both support to the International Atomic Energy Agency and bilateral exchanges. In addition, enrichment plant safeguards, especially those concerning the Gaseous Centrifuge Enrichment Plant, required a significant portion of our resources. These efforts are beginning to provide substantial returns on our investment in technology transfer

  17. Facility safeguards at an LEU fuel fabrication facility in Japan

    International Nuclear Information System (INIS)

    A facility description of a Japanese LEU BWR-type fuel fabrication plant focusing on safeguards viewpoints is presented. Procedures and practices of MC and A plan, measurement program, inventory taking, and the report and record system are described. Procedures and practices of safeguards inspection are discussed and lessons learned from past experiences are reviewed

  18. The Role of School Psychologists in Child Protection and Safeguarding

    Science.gov (United States)

    Woods, Kevin; Bond, Caroline; Tyldesley, Kath; Farrell, Peter; Humphrey, Neil

    2011-01-01

    Child protection and safeguarding are important aspects of work for all professionals working with children. The current article outlines the international context of school psychologists' work in relation to child protection and safeguarding and describes the United Kingdom context in more detail. Given the relatively recent broadening of the UK…

  19. Topical and working papers on heavy water accountability and safeguards

    International Nuclear Information System (INIS)

    This report contains the following papers: 1) Statement of IAEA concerning safeguarding of heavy water; 2) Preliminary Canadian Comments on IAEA document on heavy water safeguards; 3) Heavy water accountability 03.10.78; 4) Heavy water accountability 05.04.79

  20. 26 CFR 301.6803-1 - Accounting and safeguarding.

    Science.gov (United States)

    2010-04-01

    ... 26 Internal Revenue 18 2010-04-01 2010-04-01 false Accounting and safeguarding. 301.6803-1 Section... AND ADMINISTRATION PROCEDURE AND ADMINISTRATION General Provisions Relating to Stamps § 301.6803-1 Accounting and safeguarding. In cases coming within the provisions of section 6802 (2) and (3) and...

  1. From a Better Understanding of GRB Prompt Emission to a New Type of Standard Candles?

    Science.gov (United States)

    Guiriec, Sylvain

    2016-07-01

    Recent results revealed the simultaneous existence of multiple components in the prompt emission of gamma-ray bursts (GRBs) leading to a unified spectro-temporal model for the broadband spectrum from the optical regime up to higher gamma rays. Unexpectedly, we discovered a relation intrinsic to one specific component of this model: its luminosity is strongly and tightly correlated to its spectral break energy. This new luminosity-hardness relation has the same index for all GRBs when fitted to a power law. In addition, this relation seems to have the same normalization for all GRBs; therefore, this is a promising and physically motivated tool that may establish GRBs as cosmological standard candles. During this presentation, I will introduce this new relation, which might eventually be used to (i) estimate GRB distances, (ii) to support searches for gravitational waves and cosmic high-energy neutrinos, and (iii) constrain the cosmological parameters. I will give a few examples of GRB redshift estimates using this relation and I will show why this new result cannot solely be explain by instrumental selection effects and/or measurement/analysis biases.

  2. Type Ia Supernovae are Good Standard Candles in the Near Infrared: Evidence from PAIRITEL

    CERN Document Server

    Wood-Vasey, W Michael; Bloom, Joshua S; Hicken, Malcolm; Modjaz, Maryam; Kirshner, Robert P; Starr, Dan L; Blake, Cullen H; Falco, Emilio E; Szentgyorgyi, Andrew H; Challis, Peter; Blondin, Stephane; Rest, Armin

    2007-01-01

    We have obtained 1065 near-infrared (NIR; JHKs) measurements of 19 Type Ia supernovae (SNeIa) using PAIRITEL, the 1.3-m Peters Automated InfraRed Imaging TELescope at Mount Hopkins, Arizona. This new set of observations doubles the number of well-sampled NIR SNIa light curves. These data strengthen the evidence that SNeIa are excellent standard candles in the NIR, even without correction for light-curve shape or for reddening. We construct fiducial NIR templates for normal SNeIa from our sample, excluding only the two known peculiar SNeIa, SN 2005hk and SN 2005ke. The H-band absolute magnitudes in this sample of 17 SNe Ia have an uncorrected intrinsic RMS of only 0.14 mag. This variation is as small as the scatter in luminosity distance measurements currently used for cosmology that are based on optical light curves after corrections for light-curve shape and for dust absorption. Combining the homogeneous PAIRITEL measurements with 17 SNeIa from the literature, these 34 SNeIa have standard H-band magnitudes w...

  3. Cancer Driver Log (CanDL): Catalog of Potentially Actionable Cancer Mutations.

    Science.gov (United States)

    Damodaran, Senthilkumar; Miya, Jharna; Kautto, Esko; Zhu, Eliot; Samorodnitsky, Eric; Datta, Jharna; Reeser, Julie W; Roychowdhury, Sameek

    2015-09-01

    Massively parallel sequencing technologies have enabled characterization of genomic alterations across multiple tumor types. Efforts have focused on identifying driver mutations because they represent potential targets for therapy. However, because of the presence of driver and passenger mutations, it is often challenging to assign the clinical relevance of specific mutations observed in patients. Currently, there are multiple databases and tools that provide in silico assessment for potential drivers; however, there is no comprehensive resource for mutations with functional characterization. Therefore, we created an expert-curated database of potentially actionable driver mutations for molecular pathologists to facilitate annotation of cancer genomic testing. We reviewed scientific literature to identify variants that have been functionally characterized in vitro or in vivo as driver mutations. We obtained the chromosome location and all possible nucleotide positions for each amino acid change and uploaded them to the Cancer Driver Log (CanDL) database with associated literature reference indicating functional driver evidence. In addition to a simple interface, the database allows users to download all or selected genes as a comma-separated values file for incorporation into their own analysis pipeline. Furthermore, the database includes a mechanism for third-party contributions to support updates for novel driver mutations. Overall, this freely available database will facilitate rapid annotation of cancer genomic testing in molecular pathology laboratories for mutations. PMID:26320871

  4. Calibration of Post-AGB Supergiants as Standard Extragalactic Candles for HST

    Science.gov (United States)

    Bond, Howard E.

    1998-01-01

    This report summarizes activities carried out with support from the NASA Ultraviolet, Visible, and Gravitational Astrophysics Research and Analysis Program. The aim of the program is to calibrate the absolute magnitudes of post-asymptotic-giant-branch (post-AGB or PAGB) stars, which we believe will be an excellent new "standard candle" for measuring extragalactic distances. The reason for this belief is that in old populations, the stars that are evolving through the PAGB region of the HR (Hertzsprung-Russell) diagram arise from only a single main-sequence turnoff mass. In addition, the theoretical PAGB evolutionary tracks show that they evolve through this region at constant luminosity; hence the PAGB stars should have an extremely narrow luminosity function. Moreover, as the PAGB stars evolve through spectral types F and A (en route from the AGB to hot stellar remnants and white dwarfs), they have the highest luminosities attained by old stars (both bolometrically and in the visual band). Finally, the PAGB stars of these spectral types are very easily identified, due to their large Balmer jumps, which are due to their very low surface gravities.

  5. A Detailed Investigation into the Use of Planetary Nebulae as Standard Candles

    Science.gov (United States)

    Ciardullo, Robin

    2000-01-01

    The program's goal was to understand the physics underlying the [O III] (lambda)5007 planetary nebula luminosity function (PNLF) and evaluate its accuracy as an extragalactic distance indicator. Work under the grant concentrated in two areas. The first major goal was to extensively test the PNLF method to find its limits. We did this performing yet another internal test of the method in the core galaxies of the Fornax Cluster, performing external comparisons of PNLF distances with distances derived from Cepheids and the Surface Brightness Fluctuation method (SBF), and, in general, examining the PNLF in as many different galactic environments as possible, including the disks of late-type spirals. Because of the difficulty distinguishing planetary nebulae (PNe) from H II regions, and because spiral galaxies have uneven internal extinction, the process of identifying "statistical" samples of PNe in these objects is extremely complicated. Nevertheless, by using the ratio of [O III] (lambda)5007 to H(alpha) as a diagnostic, we were able to effectively discriminate PNe from most H II regions, and apply the method to systems such as NGC 300, M101, M51, and M96. The second goal of this research was to determine theoretically, why the PNLF is such an excellent standard candle.

  6. Dark energy constraints from joint analysis of standard rulers and standard candles

    Institute of Scientific and Technical Information of China (English)

    Marek Biesiada; Beata Malec; Aleksandra Piórkowska

    2011-01-01

    We performed joint analysis of five cosmological models invoked to explain the accelerating expansion of the Universe.We used the data from strong gravitational lensing systems, locations of cosmic microwave background acoustic peaks and baryon acoustic oscillation data in combination with supernova Ia data (Union2 compilation).The observables we used came from both standard rulers and standard candles, so they had different parameter degeneracies and different restrictive powers in the parameter spaces of cosmological models.The best fits we obtained for the model parameters in joint analysis turned out to prefer cases effectively equivalent to the ACDM model.They were also in agreement with other combined studies performed by other authors on different sets of diagnostic probes.Information theoretic methods used to assess which model is most supported by the data lead to the conclusion that the concordance model ACDM is clearly preferred in joint analysis.The quintessence (both having constant or time varying equation of state) and Chaplygin gas get considerably less support from the data while the brane world (DGP) scenario is practically ruled out.

  7. Stereoscopic Observation of Slipping Reconnection in A Double Candle-Flame-Shaped Solar Flare

    CERN Document Server

    Gou, Tingyu; Wang, Yuming; Liu, Kai; Zhuang, Bin; Chen, Jun; Zhang, Quanhao; Liu, Jiajia

    2016-01-01

    The 2011 January 28 M1.4 flare exhibits two side-by-side candle-flame-shaped flare loop systems underneath a larger cusp-shaped structure during the decay phase, as observed at the northwestern solar limb by the Solar Dynamics Observatory (SDO). The northern loop system brightens following the initiation of the flare within the southern loop system, but all three cusp-shaped structures are characterized by ~ 10 MK temperatures, hotter than the arch-shaped loops underneath. The "Ahead" satellite of the Solar Terrestrial Relations Observatory (STEREO) provides a top view, in which the post-flare loops brighten sequentially, with one end fixed while the other apparently slipping eastward. By performing stereoscopic reconstruction of the post-flare loops in EUV and mapping out magnetic connectivities, we found that the footpoints of the post-flare loops are slipping along the footprint of a hyperbolic flux tube (HFT) separating the two loop systems, and that the reconstructed loops share similarity with the magne...

  8. The charge-asymmetric nonlocally determined local-electric (CANDLE) solvation model.

    Science.gov (United States)

    Sundararaman, Ravishankar; Goddard, William A

    2015-02-14

    Many important applications of electronic structure methods involve molecules or solid surfaces in a solvent medium. Since explicit treatment of the solvent in such methods is usually not practical, calculations often employ continuum solvation models to approximate the effect of the solvent. Previous solvation models either involve a parametrization based on atomic radii, which limits the class of applicable solutes, or based on solute electron density, which is more general but less accurate, especially for charged systems. We develop an accurate and general solvation model that includes a cavity that is a nonlocal functional of both solute electron density and potential, local dielectric response on this nonlocally determined cavity, and nonlocal approximations to the cavity-formation and dispersion energies. The dependence of the cavity on the solute potential enables an explicit treatment of the solvent charge asymmetry. With four parameters per solvent, this "CANDLE" model simultaneously reproduces solvation energies of large datasets of neutral molecules, cations, and anions with a mean absolute error of 1.8 kcal/mol in water and 3.0 kcal/mol in acetonitrile. PMID:25681887

  9. Comparison of Standard Ruler and Standard Candle constraints on Dark Energy Models

    CERN Document Server

    Lazkoz, R; Perivolaropoulos, L

    2007-01-01

    We compare the dark energy model constraints obtained by using recent standard ruler data (Baryon Acoustic Oscillations (BAO) at z=0.2 and z=0.35 and Cosmic Microwave Background (CMB) shift parameters R and l_a) with the corresponding constraints obtained by using recent Type Ia Supernovae (SnIa) standard candle data (ESSENCE+SNLS+HST from Davis et. al.). We find that, even though both classes of data are consistent with LCDM at the 2\\sigma level, there is a systematic difference between the two classes of data. In particular, we find that for practically all values of the parameters (\\Omega_0m,\\Omega_b) in the 2\\sigma range of the the 3-year WMAP data (WMAP3) best fit, LCDM is significantly more consistent with the SnIa data than with the CMB+BAO data. For example for (\\Omega_0m,\\Omega_b)=(0.24,0.042) corresponding to the best fit values of WMAP3, the dark energy equation of state parametrization w(z)=w_0 + w_1 (z/(1+z)) best fit is at a 0.5\\sigma distance from LCDM (w_0=-1,w_1=0) using the SnIa data and 1.7...

  10. Synergy on safeguards safety and security

    International Nuclear Information System (INIS)

    Nuclear energy for prosperity and peaceful purposes can be realized effectively and transparently if components such as safeguards safety and security are integrated in a one unit of infrastructure. Coordinating of them within a fuel cycle life commencing from concept design to decommissioning is necessity to ensure that worker, communities and environment are fully protected from radiation hazard and also to ensure that facility and nuclear material are merely for peaceful purposes. This paper is aim to assess similarity and differences among them so as to identify potential synergy exist and its challenges appear. The assessment is conducted by reviewing several libraries and combining it with experiences gain during working at the field of nuclear technology. It is noticed that synergy among safety, security and safeguards have not been yet implemented in most of nuclear installations. Each of them is developed and realized separately and has not yet to integrate become a one unit infrastructure. Synergy and integration all the above components are important to ensure worker, communities and environment are fully protected from radiation hazard and also to ensure that peaceful purposes of nuclear material usage is fulfilled. (author)

  11. Electrochemically Modulated Separation for Plutonium Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Pratt, Sandra H.; Breshears, Andrew T.; Arrigo, Leah M.; Schwantes, Jon M.; Duckworth, Douglas C.

    2013-12-31

    Accurate and timely analysis of plutonium in spent nuclear fuel is critical in nuclear safeguards for detection of both protracted and rapid plutonium diversions. Gamma spectroscopy is a viable method for accurate and timely measurements of plutonium provided that the plutonium is well separated from the interfering fission and activation products present in spent nuclear fuel. Electrochemically modulated separation (EMS) is a method that has been used successfully to isolate picogram amounts of Pu from nitric acid matrices. With EMS, Pu adsorption may be turned "on" and "off" depending on the applied voltage, allowing for collection and stripping of Pu without the addition of chemical reagents. In this work, we have scaled up the EMS process to isolate microgram quantities of Pu from matrices encountered in spent nuclear fuel during reprocessing. Several challenges have been addressed including surface area limitations, radiolysis effects, electrochemical cell performance stability, and chemical interferences. After these challenges were resolved, 6 µg Pu was deposited in the electrochemical cell with approximately an 800-fold reduction of fission and activation product levels from a spent nuclear fuel sample. Modeling showed that these levels of Pu collection and interference reduction may not be sufficient for Pu detection by gamma spectroscopy. The main remaining challenges are to achieve a more complete Pu isolation and to deposit larger quantities of Pu for successful gamma analysis of Pu. If gamma analyses of Pu are successful, EMS will allow for accurate and timely on-site analysis for enhanced Pu safeguards.

  12. All Mexican atomic work to be safeguarded

    International Nuclear Information System (INIS)

    Mexico has become the first nation which has agreed to place its entire nuclear programme under the Agency's supervision to ensure that the work is entirely for peaceful purposes. It has taken this step in accordance with the Treaty of Tlatelolco, under which 21 States in Latin America agreed in February 1967 to create a nuclear-free zone by banning nuclear weapons. An agreement putting Mexico's acceptance of safeguards supervision into effect was signed in Vienna on 6 September by the Mexican Under-Secretary for Foreign Affairs, Ambassador Alfonso Garcia Robles. The total number of safeguards agreements is now 40 and involves 30 Member States. During the General Conference Turkey accepted control of its co-operative atomic activities with the USA, which have been in progress since 1955. Ambassador Hassan Istinyeli, Member for Turkey of the Board of Governors and Resident Representative to the Agency, Ambassador H. D. Smyth, USA Member of the Board of Governors and Dr. Eklund were the signatories. (author)

  13. Technology guidance for safeguards information management

    Energy Technology Data Exchange (ETDEWEB)

    Manatt, D.R. [Lawrence Livermore National Lab., CA (United States); Howell, J.A. [Los Alamos National Lab., NM (United States); Steinmaus, K.; St. Pierre, D. [Pacific Northwest Lab., Richland, WA (United States); Deland, S.M.; Vandewart, R. [Sandia National Labs., Albuquerque, NM (United States)

    1994-09-01

    The Safeguards Information Management Systems project, SIMS, seeks to provide information access tools to the IAEA to assist in implementation of enhanced safeguards. The Technology and Systems Group advises the SIMS project in the selection of hardware and software, the integration of system components, and the evaluation of realistic information management approaches. The group`s guidance has led to reevaluation of the system hardware choices, visual data storage methods, and geographical data sources. Consultation with the Agency has resulted in a major realignment of the effort towards providing information access on Networked Microsoft Windows desk top computers rather than separate SUN workstations. The manner in which imagery is stored and presented is another developing area. Initial systems delivered to the Agency relied on analogue video disc recorders and VCRs. Future systems will store and manipulate digital images. The initial source of map data for the workstation was analogue video discs from the US Defense Mapping Agency. Many of these maps are restricted in their distribution, therefore additional map data sources were developed. The Technology map data sources were developed. The Technology and Systems Group`s efforts to steer a clear course through this ever changing mine-field is described.

  14. Technology development of nuclear material safeguards for DUPIC fuel cycle

    International Nuclear Information System (INIS)

    During the second phase of research and development program conducted from 1993 to 1996, nuclear material safeguards studies system were performed on the technology development of DUPIC safeguards system such as nuclear material measurement in bulk form and product form, DUPIC fuel reactivity measurement, near-real-time accountancy, and containment and surveillance system for effective and efficient implementation of domestic and international safeguards obligation. By securing in advance a optimized safeguards system with domestically developed hardware and software, it will contribute not only to the effective implementation of DUPIC safeguards, but also to enhance the international confidence build-up in peaceful use of spent fuel material. (author). 27 refs., 13 tabs., 89 figs

  15. Safeguardability of the vitrification option for disposal of plutonium

    Energy Technology Data Exchange (ETDEWEB)

    Pillay, K.K.S. [Los Alamos National Lab., NM (United States)

    1996-05-01

    Safeguardability of the vitrification option for plutonium disposition is rather complex and there is no experience base in either domestic or international safeguards for this approach. In the present treaty regime between the US and the states of the former Soviet Union, bilaterial verifications are considered more likely with potential for a third-party verification of safeguards. There are serious technological limitations to applying conventional bulk handling facility safeguards techniques to achieve independent verification of plutonium in borosilicate glass. If vitrification is the final disposition option chosen, maintaining continuity of knowledge of plutonium in glass matrices, especially those containing boron and those spike with high-level wastes or {sup 137}Cs, is beyond the capability of present-day safeguards technologies and nondestructive assay techniques. The alternative to quantitative measurement of fissile content is to maintain continuity of knowledge through a combination of containment and surveillance, which is not the international norm for bulk handling facilities.

  16. Developing the information management system for safeguards national inspection

    Energy Technology Data Exchange (ETDEWEB)

    Park, S. J.; Jeon, I.; Park, W. S.; Min, K. S. [KAERI, Taejon (Korea, Republic of)

    2003-10-01

    The inspection information management system for safeguards national inspection is aimed to do the national safeguards inspection with efficiency, and to decrease the inspector's load to write inspection report by systematizing the inspection jobs and sharing the inspection data. National safeguards inspection is consisted two large jobs. The first is the national safeguards supporting job of managing to support the national inspection mission. The other is the writing a national inspection report after completing the national inspection. Before the developing of inspection information management system, the official tools(spread sheet, word processor) are usually used. But there is problem to share the data, to produce the statistics data. To solve the these problem, we developed the inspection information management system that process the job from initial to final inspection work, and opened user education. This paper explain the procedure of developing the inspection information management system for safeguards national inspection.

  17. Technology transfer significance of the International Safeguards Project Office

    Energy Technology Data Exchange (ETDEWEB)

    Marcuse, W.; Waligura, A.J.

    1988-06-01

    The safeguards implemented by the International Atomic Energy Agency (IAEA) are of major importance to the non-proliferation objectives of the United States of America and other nations of the world. Assurance of safeguards effectiveness is mandatory to continued peaceful use of nuclear power. To enhance the ability of the IAEA to apply safeguards effectively, and to ensure that the IAEA does not lack technical assistance in critical areas, the US Congress has made available a special authorization for a Program for Technical Assistance to IAEA Safeguards (POTAS). This substantial program of technology transfer was initiated in 1976. The United States Departments of State and Energy, the Arms control and Disarmament Agency and the Nuclear Regulatory Commission have each accepted responsibility for parts of the Program for Technical Assistance to IAEA Safeguards. Funding is provided by state through the Foreign Assistance Act. This report provides a discussion of this program.

  18. Technology development of nuclear material safeguards for DUPIC fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Jong Sook; Kim, Ho Dong; Kang, Hee Young; Lee, Young Gil; Byeon, Kee Ho; Park, Young Soo; Cha, Hong Ryul; Park, Ho Joon; Lee, Byung Doo; Chung, Sang Tae; Choi, Hyung Rae; Park, Hyun Soo

    1997-07-01

    During the second phase of research and development program conducted from 1993 to 1996, nuclear material safeguards studies system were performed on the technology development of DUPIC safeguards system such as nuclear material measurement in bulk form and product form, DUPIC fuel reactivity measurement, near-real-time accountancy, and containment and surveillance system for effective and efficient implementation of domestic and international safeguards obligation. By securing in advance a optimized safeguards system with domestically developed hardware and software, it will contribute not only to the effective implementation of DUPIC safeguards, but also to enhance the international confidence build-up in peaceful use of spent fuel material. (author). 27 refs., 13 tabs., 89 figs.

  19. Parental Traffic Safeguarding at School Sites: Unequal Risks and Responsibilities

    Directory of Open Access Journals (Sweden)

    Arlene Tigar McLaren

    2011-01-01

    Full Text Available Scholars recognize the importance of parental chauffeuring in urbanenvironments, but pay remarkably little attention to how parents, as part of everyday, domestic practices, safeguard their children in auto-dominated streets. Based on in-depth, qualitative interviews with parents whose children attend public elementary schools, this exploratory study compares traffic safeguarding experiences on the east and west sides of Vancouver, British Columbia. The analysisshows how social class and gender intersect in three traffic sites: school streetscapes, school entrances, and school traffic safety volunteerism. Utilizing automobility and feminist theories, we argue that urban parental traffic safeguarding is a complex and variegated phenomenon involving unequal risks and responsibilities. Our analysis illustrates the ways in which parental traffic safeguarding is a lynchpin to the automobility system, particularly with respect to itsillusion of safety, and how, conversely, this system shapes parenting by constituting traffic safeguarding as part of domestic responsibilities.

  20. Safeguards and security progress report, January-December 1985

    International Nuclear Information System (INIS)

    From January to December 1985, the Los Alamos Safeguards and Security Program was involved in the activities described in the first four parts of this report: Safeguards Operations, Security Development and Support, Safeguards Technology Development, and International Support. Part 1 covers efforts of direct assistance to the Department of Energy and Nuclear Regulatory Commission licensee facilities. This assistance includes consultation on materials accounting problems, development and demonstration of specialized techniques and instruments, and comprehensive participation in the design and evaluation of advanced safeguards systems. In addition, a series of training courses in various aspects of safeguards makes the technology more accessible to those who must apply it. Part 2 treats activities aimed at the security of information and computer systems. Our focus this period was on continuing the activities of the Center for Computer Security, which provides the basis for encouraging and disseminating this emerging technology, and on the development and demonstration of secure computer systems. Part 3 describes the broad development efforts essential to continuing improvements in the practice of safeguards. Although these projects are properly classified as developmental, they address recognized problems that commonly occur in operating facilities. Finally, Part 4 covers international safeguards activities, including both support to the International Atomic Energy Agency and bilateral exchanges. Enrichment plant safeguards and international safeguards for reprocessing plants required a significant portion of our resources. All of these efforts are beginning to provide substantial returns on our investment in technology transfer, not only in raising the level of safeguards effectiveness but also in our benefiting from field experiences in operating environments

  1. Safeguards and security progress report, January-December 1985

    Energy Technology Data Exchange (ETDEWEB)

    1987-03-01

    From January to December 1985, the Los Alamos Safeguards and Security Program was involved in the activities described in the first four parts of this report: Safeguards Operations, Security Development and Support, Safeguards Technology Development, and International Support. Part 1 covers efforts of direct assistance to the Department of Energy and Nuclear Regulatory Commission licensee facilities. This assistance includes consultation on materials accounting problems, development and demonstration of specialized techniques and instruments, and comprehensive participation in the design and evaluation of advanced safeguards systems. In addition, a series of training courses in various aspects of safeguards makes the technology more accessible to those who must apply it. Part 2 treats activities aimed at the security of information and computer systems. Our focus this period was on continuing the activities of the Center for Computer Security, which provides the basis for encouraging and disseminating this emerging technology, and on the development and demonstration of secure computer systems. Part 3 describes the broad development efforts essential to continuing improvements in the practice of safeguards. Although these projects are properly classified as developmental, they address recognized problems that commonly occur in operating facilities. Finally, Part 4 covers international safeguards activities, including both support to the International Atomic Energy Agency and bilateral exchanges. Enrichment plant safeguards and international safeguards for reprocessing plants required a significant portion of our resources. All of these efforts are beginning to provide substantial returns on our investment in technology transfer, not only in raising the level of safeguards effectiveness but also in our benefiting from field experiences in operating environments.

  2. Development of nuclear material accounting and safeguards technology

    Energy Technology Data Exchange (ETDEWEB)

    Shin, H. S.; Kim, H. D.; Park, K. J; and others

    2012-04-15

    The objective of this project is to analyze the safeguard ability of pyroprocess facility and to establish the safeguards system for pyroprocess by developing the technology of nuclear material accounting for unit process, surveillance technology and nuclear characteristics analysis technology which are needed to demonstrate the safeguards technology of pyroprocess. In order to establish the nuclear material accountancy for PRIDE the unified NDA was designed by integrating neutron detection, gamma ray detection, and mass measurement. The surveillance system of PRIDE includes gamma ray detector system for tracing the position of nuclear material in PRIDE and the safeguards system was designed considering the characteristics of nuclear material accountancy and surveillance equipment and monitoring the main factors of process equipment. Based on the design of safeguards system for PRIDE a simulation program for the integrated accounting and surveillance information system has been developed and tested. The safeguard ability analysis code for pyroprocessing facility has been designed to develop a Pyroprocessing Material flow and Material Unaccounted For Uncertainty Simulation (PYMUS) program based on the result from safeguard ability analysis by ROK IAEA MSSP. For novel technologies development of nuclear material accountancy by domestic and international cooperation, the application of XRF, SINRD, PNAR, FRAM, LIBS to NMA has been studied. The safeguards system of PRIDE will be referred to verify the safeguards approach and implementation techniques for pyroprocessing facility on international cooperation(ROK US Joint Fuel Cycle Study and ROK IAEA Member State Support Program). The results of this project will contribute to increase the nuclear transparency for realizing the pyroprocessing technology of the ROK as well as to establish the safeguards technology for pyroprocessing facility.

  3. Third International Meeting on Next Generation Safeguards:Safeguards-by-Design at Enrichment Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Long, Jon D. [Y-12 National Security Complex; McGinnis, Brent R [ORNL; Morgan, James B [ORNL; Whitaker, Michael [ORNL; Lockwood, Mr. Dunbar [U.S. Department of Energy, NNSA; Shipwash, Jacqueline L [ORNL

    2011-01-01

    The Third International Meeting on Next Generation Safeguards (NGS3) was hosted by the U.S. Department of Energy (DOE)/National Nuclear Security Administration's (NNSA) Office of Nonproliferation and International Security (NIS) in Washington, D.C. on 14-15 December 2010; this meeting focused on the Safeguards-by-Design (SBD) concept. There were approximately 100 participants from 13 countries, comprised of safeguards policy and technical experts from government and industry. Representatives also were present from the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC), the European Atomic Energy Agency (Euratom), and the International Atomic Energy Agency (IAEA). The primary objective of this meeting was to exchange views and provide recommendations on implementation of the SBD concept for four specific nuclear fuel cycle facility types: gas centrifuge enrichment plants (GCEPs), GEN III and GEN IV reactors, aqueous reprocessing plants, and mixed oxide fuel fabrication facilities. The general and facility-specific SBD documents generated from the four working groups, which were circulated for comment among working group participants, are intended to provide a substantive contribution to the IAEA's efforts to publish SBD guidance for these specific types of nuclear facilities in the near future. The IAEA has described the SBD concept as an approach in which 'international safeguards are fully integrated into the design process of a new nuclear facility from the initial planning through design, construction, operation, and decommissioning.' As part of the Next Generation Safeguards Initiative (NGSI), the DOE is working to establish SBD as a global norm through DOE laboratory studies, international workshops, engagement with industry and the IAEA, and setting an example through its use in new nuclear facilities in the United States. This paper describes the discussion topics and final recommendations of the Enrichment

  4. Internal safeguards for centrifuge enrichment plants. Concepts and procedures for safeguards and the international Hexapartite Safeguards Project (HSP)

    International Nuclear Information System (INIS)

    These papers were elaborated partly as annexes to the HSP and partly within a BMFT research programme. Chapter 2 shows how the HSP is to be proceeded with and describes the inspection activities agreed upon. Chapters 3 and 4 deal with the nuclear materials accountancy in a uranium enrichment plant; the conception of a computer-aided safeguards system (chapter 4) can only be given in condensed form owing to its size. Chapter 5 is a general evaluation of now available NDA and C/S systems whereas chapters 6 and 7 indicate fields of application for specialized technologies. Even though the inspection model agreed upon as a result of the HSP discussions is to include limited frequency unannounced access to separating rooms for inspectors, theoretical and experimental studies have been carried out in the meantime assuming the non-access model. (orig./HP)

  5. IAEA Safeguards in Pakistan and Emerging Issues/Challenges

    International Nuclear Information System (INIS)

    Implementation of IAEA Safeguards in Pakistan dates back to March, 1962 when a trilateral safeguards agreement (INFCIRC/34) was signed for the supply of Pakistan Research Reactor-1 (PARR-1). Since then Pakistan has concluded several safeguards agreements with the Agency. All the safeguards agreements concluded by Pakistan are governed under the Safeguards Document INFCIRC/66/Rev.2, which is a model for countries not party to NPT (Treaty on the Non-Proliferation of Nuclear Weapons). As per this model the item-specific safeguards are applied to Pakistan's nuclear facilities. Being a 66-type country, some times, very peculiar nature of safeguards issues arise that are not common in the States with Comprehensive Safeguards Agreement (CSA) and which pose challenges for both the IAEA and the country. In Pakistan, not only nuclear material, but non-nuclear material is also subjected to safeguards under the respective Safeguards Agreement. At KANUPP, for example, the heavy water used as moderator and coolant, is under IAEA safeguards. The Suspension and Termination options of INFCIRC/66/Rev.2 are atypical from comprehensive safeguards and are utilized in Pakistan to resolve various issues. For example, the HEU plates are targeted in a safeguarded research reactor (PARR-1) for Mo-99 production, which are then separated in an unsafeguarded Moly Production Plant employing the suspension clause of INFCIRC/66/Rev.2. The Additional Protocol substantially enlarges the IAEA's ability to check for clandestine nuclear activities and facilities. The requirements of the Model Additional Protocol are basically designed for the non-nuclear-weapon states-parties to the NPT; the nuclear weapon states are, however, free to choose among or limit the application of the provisions of the Model Additional Protocol. The INFCIRC/66/Rev.2 countries (countries not party to the NPT) may analyse the impact to their programme, of adhering to the Additional Protocol. However, INFCIRC/66/Rev.2

  6. Development Status and Trend of Global Candle Market%全球蜡烛市场发展现状及趋势

    Institute of Scientific and Technical Information of China (English)

    孙东方

    2012-01-01

    蜡烛作为传统的商品发展到今天,已经不再是传统照明的蜡烛,在科技的推动下,蜡烛及其制品行业已经走进一个全新的领域,形成一个具有巨大市场潜力的行业.目前欧美市场作为全球最重要的蜡烛消费区域,通过对全球蜡烛市场进行分析与预测,为国内蜡烛制造企业的发展提供参考依据.%Candles as traditional goods are no longer just the traditional lighting products today.With development of the technology,candle industry has entered a new field,and formed an industry with huge market potential.Nowadays,U.S.and European markets have been the most important candle consumer areas.In the paper,the global candle market was analyzed and forecasted,which can provide a reference for development of the domestic candle manufacturing enterprises.

  7. The European Safeguards Research and Development Association Addresses Safeguards and Nonproliferation

    International Nuclear Information System (INIS)

    The renaissance of efforts to expand the use of nuclear energy requires the parallel development of a renewed and more sophisticated work force. Growth in the nuclear sector with high standard of safety, safeguards and security requires skilled staff for design, operations, inspections etc. High-quality nuclear technology educational programs are diminished from past years, and the ability of universities to attract students and to meet future staffing requirements of the nuclear industry is becoming seriously compromised. Thus, education and training in nuclear engineering and sciences is one of the cornerstones for the nuclear sector. Teaching in the nuclear field still seems strongly influenced by national history but it is time to strengthen resources and collaborate. Moreover with the current nuclear security threats it becomes critical that nuclear technology experts master the basic principles not only of safety, but also of nuclear safeguards, nonproliferation and nuclear security. In Europe the European Nuclear Education Network (ENEN) Association has established the certificate 'European Master of Science in Nuclear Engineering (EMSNE)' as the classic nuclear engineering program covering reactor operation and nuclear safety. However, it does not include courses on nonproliferation, safeguards, or dual-use technologies. The lack of education in nuclear safeguards was tackled by the European Safeguards Research and Development Association (ESARDA), through development and implementation of safeguards course modules. Since 2005 the ESARDA Working Group, called the Training and Knowledge Management Working Group, (TKMWG) has worked with the Joint Research Centre (JRC) in Ispra, Italy to organize a Nuclear Safeguards and Nonproliferation course. This five-day course is held each spring at the JRC, and continues to show increasing interest as evidenced by the positive responses of international lecturers and students. The standard set of lectures covers a broad

  8. The European Safeguards Research and Development Association Addresses Safeguards and Nonproliferation

    Energy Technology Data Exchange (ETDEWEB)

    Janssens-Maenhout, Greet; Kusumi, R.; Daures, Pascal A.; Janssens, Willem; Dickman, Deborah A.

    2010-06-16

    The renaissance of efforts to expand the use of nuclear energy requires the parallel development of a renewed and more sophisticated work force. Growth in the nuclear sector with high standard of safety, safeguards and security requires skilled staff for design, operations, inspections etc. High-quality nuclear technology educational programs are diminished from past years, and the ability of universities to attract students and to meet future staffing requirements of the nuclear industry is becoming seriously compromised. Thus, education and training in nuclear engineering and sciences is one of the cornerstones for the nuclear sector. Teaching in the nuclear field still seems strongly influenced by national history but it is time to strengthen resources and collaborate. Moreover with the current nuclear security threats it becomes critical that nuclear technology experts master the basic principles not only of safety, but also of nuclear safeguards, nonproliferation and nuclear security. In Europe the European Nuclear Education Network (ENEN) Association has established the certificate 'European Master of Science in Nuclear Engineering (EMSNE)' as the classic nuclear engineering program covering reactor operation and nuclear safety. However, it does not include courses on nonproliferation, safeguards, or dual-use technologies. The lack of education in nuclear safeguards was tackled by the European Safeguards Research and Development Association (ESARDA), through development and implementation of safeguards course modules. Since 2005 the ESARDA Working Group, called the Training and Knowledge Management Working Group, (TKMWG) has worked with the Joint Research Centre (JRC) in Ispra, Italy to organize a Nuclear Safeguards and Nonproliferation course. This five-day course is held each spring at the JRC, and continues to show increasing interest as evidenced by the positive responses of international lecturers and students. The standard set of lectures

  9. Comparison of high efficiency particulate filter testing methods

    International Nuclear Information System (INIS)

    High Efficiency Particulate Air (HEPA) filters are used for the removal of submicron size particulates from air streams. In nuclear industry they are used as an important engineering safeguard to prevent the release of air borne radioactive particulates to the environment. HEPA filters used in the nuclear industry should therefore be manufactured and operated under strict quality control. There are three levels of testing HEPA filters: i) testing of the filter media; ii) testing of the assembled filter including filter media and filter housing; and iii) on site testing of the complete filter installation before putting into operation and later for the purpose of periodic control. A co-ordinated research programme on particulate filter testing methods was taken up by the Agency and contracts were awarded to the Member Countries, Belgium, German Democratic Republic, India and Hungary. The investigations carried out by the participants of the present co-ordinated research programme include the results of the nowadays most frequently used HEPA filter testing methods both for filter medium test, rig test and in-situ test purposes. Most of the experiments were carried out at ambient temperature and humidity, but indications were given to extend the investigations to elevated temperature and humidity in the future for the purpose of testing the performance of HEPA filter under severe conditions. A major conclusion of the co-ordinated research programme was that it was not possible to recommend one method as a reference method for in situ testing of high efficiency particulate air filters. Most of the present conventional methods are adequate for current requirements. The reasons why no method is to be recommended were multiple, ranging from economical aspects, through incompatibility of materials to national regulations

  10. International safeguards for fast critical facilities

    Energy Technology Data Exchange (ETDEWEB)

    Gunderson, D.O.; Todd. J.L.

    1978-12-01

    It was concluded that practical routine inventory verification techniques can be effective in detecting protracted diversion but will not meet the seven-day timeliness criteria either for protracted or large one-time diversions. An effective international safeguards system requires a method of continuously monitoring facility activities either with instrumentation, inspectors, or a combination thereof. It was also concluded that a resident inspector is required at this type of facility because of the many nonroutine operations. However, a single inspector cannot adequately monitor all activities to assure that no diversion is taking place. The use of existing structural features and unattended monitoring at portals as well as surveillance by a resident inspector can provide an effective detection capability. A rapid special inventory verification is required following detection to verify any suspected diversion.

  11. Open Source Information in Support of Safeguards

    International Nuclear Information System (INIS)

    Open source techniques are an increasingly important tool for in safeguards. From social networking sites, such as Linkedin, to B2B portals like Alibaba, there are large open source databases that touch all aspects of the nuclear fuel cycle, from goods to scientists. This is in addition to the wealth of more traditional open source tools such as search engines. In this paper we focus on the potential of B2B sites to provide dual use goods for use in the nuclear fuel cycle. We will discuss the availability of these items as well as the frequency and content of tenders. As many of the largest sites—by traffic and content—are in Asia we will examine the potential of these sites to provide goods used in the nuclear fuel cycle. (author)

  12. Implementation of ion based applications for safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Martinez, R.L.; Johnson, C.S.

    1996-08-01

    The uses of the LON, `Local Operating Network,` developed by Echelon Corporation, Palo Alto, California, has been expanded to handle a number of safeguards applications. A magnetic and vibration sensor pack has been developed to monitor for magnetic fields and vibration. This sensor pack can be attached to any source that generates a magnetic field, such as electrical solenoids or motors, to detect when the source is activated. New network nodes that interface directly with the raw data of Sandia developed radiation sensors, for detecting the presence of radiation sources, have been developed. The capacity of the network has been expanded to allow the transmission of large data sets, specifically the transmission of digital video images from the Sandia-developed-Image Compression and Authentication Module (ICAM).

  13. Design of safeguards systems for authentication

    International Nuclear Information System (INIS)

    Full text: To permit valid conclusions to be drawn from safeguards data, it is essential that this data be authentic. That is, it must be known that the data originated from the intended source, that the data was not changed in transit and that it is not a repeat or delayed copy of previous data. Furthermore a compromise of the source must not permit new trusted data to be generated and should not invalidate previous data. Authentication should be designed into safeguards systems instead of being added later. Failure to integrate authentication early in the design results in systems that are expensive or possibly impossible to deploy securely. This paper gives some of the factors that should be considered and some of the methods that can be employed for ensuring high security while minimizing cost. The paper is a compilation of some of the lessons learned by the authors during the last few years of working with the authentication of these systems. Examples are given of approaches that worked well and some that the authors found less successful. More use is being made of unattended and remote monitoring, and more facilities are becoming heavily automated. In some cases sensors and data generators may be deployed in many locations within a facility and may not be easily accessed (or may be located in hazardous locations). Because of these factors, physical access is becoming more limited, so safeguards systems must be designed to maximize reliability and to minimize inspection and maintenance time. For example, tamper indicating enclosures are only effective when they are adequately inspected, thus the number, size, and complexity of tamper indicating enclosures should be minimized. This might be accomplished by applying cryptographic data authentication at the sensor thus avoiding the need to install tamper indicating conduit (The inspection of long runs of conduit is difficult and expensive.) The proper use of standard internationally accepted protocols for data

  14. Application of virtualised reality to safeguards

    International Nuclear Information System (INIS)

    For several years the JRC has been working with laser range finders aiming at the complete 3D reconstruction of real environments 'as built'. This technique is known as Virtualised Reality. By scanning the environment with a laser range finder, a map of the distances is acquired. This 'depth map' is at the basis of the 3D model to be created. 3D data analysis can detect and resolve occlusions, i.e., it can detect regions which are hidden and thus cannot modelled from a particular capture point. The 3D model is automatically textured with photographic quality pictures from the environment itself. The final complete model is encoded in the VRML format and can be accessed by inspectors with a standard Web browser. The paper describes the technique used for building the complete 3D models from reality, the corresponding accuracy, and will focus on immediate and future applications for Safeguards, in particular training and design information verification. (author)

  15. Safeguards and security progress report, January-December 1984

    International Nuclear Information System (INIS)

    From January to December 1984, the Los Alamos Safeguards and Security Program was involved in the activities described in the first four parts of this report: Nuclear Facility Support, Security Development and Support, Safeguards Technology Development, and International Safeguards. Part 1 covers efforts of direct assistance to the Department of Energy (DOE) and Nuclear Regulatory Commission (NRC) licensee facilities. Part 2 treats activities aimed at the security of information and computer systems. was Part 3 describes the broad development efforts essential to continuing improvements in the practice of safeguards. Although these projects are properly classified as developmental, they address recognized problems that commonly occur in operating facilities. Finally, Part 4 covers international safeguards activities, including both support to the International Atomic Energy Agency and bilateral exchanges. Enrichment plant safeguards, especially those concerning the Gas Centrifuge Enrichment Plant, required a significant portion of our resources. These efforts are beginning to provide substantial returns on our investment in technology transfer, not only in raising the level of safeguards effectiveness but also in benefiting from field experiences in operating environments

  16. Safeguards and security progress report, January-December 1984

    Energy Technology Data Exchange (ETDEWEB)

    Smith, D.B. (comp.)

    1986-01-01

    From January to December 1984, the Los Alamos Safeguards and Security Program was involved in the activities described in the first four parts of this report: Nuclear Facility Support, Security Development and Support, Safeguards Technology Development, and International Safeguards. Part 1 covers efforts of direct assistance to the Department of Energy (DOE) and Nuclear Regulatory Commission (NRC) licensee facilities. Part 2 treats activities aimed at the security of information and computer systems. was Part 3 describes the broad development efforts essential to continuing improvements in the practice of safeguards. Although these projects are properly classified as developmental, they address recognized problems that commonly occur in operating facilities. Finally, Part 4 covers international safeguards activities, including both support to the International Atomic Energy Agency and bilateral exchanges. Enrichment plant safeguards, especially those concerning the Gas Centrifuge Enrichment Plant, required a significant portion of our resources. These efforts are beginning to provide substantial returns on our investment in technology transfer, not only in raising the level of safeguards effectiveness but also in benefiting from field experiences in operating environments.

  17. Analysis of the impact of safeguards criteria

    International Nuclear Information System (INIS)

    As part of the US Program of Technical Assistance to IAEA Safeguards, the Pacific Northwest Laboratory (PNL) was asked to assist in developing and demonstrating a model for assessing the impact of setting criteria for the application of IAEA safeguards. This report presents the results of PNL's work on the task. The report is in three parts. The first explains the technical approach and methodology. The second contains an example application of the methodology. The third presents the conclusions of the study. PNL used the model and computer programs developed as part of Task C.5 (Estimation of Inspection Efforts) of the Program of Technical Assistance. The example application of the methodology involves low-enriched uranium conversion and fuel fabrication facilities. The effects of variations in seven parameters are considered: false alarm probability, goal probability of detection, detection goal quantity, the plant operator's measurement capability, the inspector's variables measurement capability, the inspector's attributes measurement capability, and annual plant throughput. Among the key results and conclusions of the analysis are the following: the variables with the greatest impact on the probability of detection are the inspector's measurement capability, the goal quantity, and the throughput; the variables with the greatest impact on inspection costs are the throughput, the goal quantity, and the goal probability of detection; there are important interactions between variables. That is, the effects of a given variable often depends on the level or value of some other variable. With the methodology used in this study, these interactions can be quantitatively analyzed; reasonably good approximate prediction equations can be developed using the methodology described here

  18. Safeguards and security progress report, January-December 1983

    Energy Technology Data Exchange (ETDEWEB)

    Smith, D.B. (comp.)

    1984-09-01

    From January to December 1983, the Los Alamos Safeguards and Security Program was involved in the activities described in the first four parts of this report: Nuclear Facility Support, Security Development and Support, Safeguards Technology Development, and International Safeguards. Part 1 covers efforts of direct assistance to the Department of Energy (DOE) and Nuclear Regulatory Commission (NRC) licensee facilities. This assistance includes consultation on materials accounting problems, development of specialized techniques and instruments, and comprehensive participation in the design and implementation of advanced safeguards systems. In addition, a series of training courses in various aspects of safeguards makes the technology more accessible to those who must apply it. Part 2 treats activities aimed at the security of information and computer systems. Our focus this peiod was on continuing the activities of the Computer Security Center, which provides the basis for encouraging and disseminating this emerging technology, and on the development and demonstration of secure computer systems. Part 3 describes the broad development efforts essential to continuing improvements in the practice of safeguards. Although these projects are properly classified as developmental, they address recognized problems that commonly occur in operating facilities. Finally, Part 4 covers international safeguards activities, including both support to the International Atomic Energy Agency and bilateral exchanges. Enrichment plant safeguards, especially those concerning the Gas Centrifuge Enrichment Plant, required a significant portion of our resources. These efforts are beginning to provide substantial returns on our investment in technology transfer, not only in raising the level of safeguards effectiveness but also in our benefiting from field experiences in operating environments.

  19. Safeguards and security progress report, January-December 1983

    International Nuclear Information System (INIS)

    From January to December 1983, the Los Alamos Safeguards and Security Program was involved in the activities described in the first four parts of this report: Nuclear Facility Support, Security Development and Support, Safeguards Technology Development, and International Safeguards. Part 1 covers efforts of direct assistance to the Department of Energy (DOE) and Nuclear Regulatory Commission (NRC) licensee facilities. This assistance includes consultation on materials accounting problems, development of specialized techniques and instruments, and comprehensive participation in the design and implementation of advanced safeguards systems. In addition, a series of training courses in various aspects of safeguards makes the technology more accessible to those who must apply it. Part 2 treats activities aimed at the security of information and computer systems. Our focus this peiod was on continuing the activities of the Computer Security Center, which provides the basis for encouraging and disseminating this emerging technology, and on the development and demonstration of secure computer systems. Part 3 describes the broad development efforts essential to continuing improvements in the practice of safeguards. Although these projects are properly classified as developmental, they address recognized problems that commonly occur in operating facilities. Finally, Part 4 covers international safeguards activities, including both support to the International Atomic Energy Agency and bilateral exchanges. Enrichment plant safeguards, especially those concerning the Gas Centrifuge Enrichment Plant, required a significant portion of our resources. These efforts are beginning to provide substantial returns on our investment in technology transfer, not only in raising the level of safeguards effectiveness but also in our benefiting from field experiences in operating environments

  20. Standard Rulers, Candles, and Clocks from the Low-Redshift Universe

    Science.gov (United States)

    Heavens, Alan; Jimenez, Raul; Verde, Licia

    2014-12-01

    We measure the length of the baryon acoustic oscillation (BAO) feature, and the expansion rate of the recent Universe, from low-redshift data only, almost model independently. We make only the following minimal assumptions: homogeneity and isotropy, a metric theory of gravity, a smooth expansion history, and the existence of standard candles (supernovæ) and a standard BAO ruler. The rest is determined by the data, which are compilations of recent BAO and type IA supernova results. Making only these assumptions, we find for the first time that the standard ruler has a length of 103.9 ±2.3 h-1 Mpc . The value is a measurement, in contrast to the model-dependent theoretical prediction determined with model parameters set by Planck data (99.3 ±2.1 h-1 Mpc ). The latter assumes the cold dark matter model with a cosmological constant, and that the ruler is the sound horizon at radiation drag. Adding passive galaxies as standard clocks or a local Hubble constant measurement allows the absolute BAO scale to be determined (142.8 ±3.7 Mpc ), and in the former case the additional information makes the BAO length determination more precise (101.9 ±1.9 h-1 Mpc ). The inverse curvature radius of the Universe is weakly constrained and consistent with zero, independently of the gravity model, provided it is metric. We find the effective number of relativistic species to be Neff=3.53 ±0.32 , independent of late-time dark energy or gravity physics.

  1. Standard rulers, candles, and clocks from the low-redshift universe.

    Science.gov (United States)

    Heavens, Alan; Jimenez, Raul; Verde, Licia

    2014-12-12

    We measure the length of the baryon acoustic oscillation (BAO) feature, and the expansion rate of the recent Universe, from low-redshift data only, almost model independently. We make only the following minimal assumptions: homogeneity and isotropy, a metric theory of gravity, a smooth expansion history, and the existence of standard candles (supernovæ) and a standard BAO ruler. The rest is determined by the data, which are compilations of recent BAO and type IA supernova results. Making only these assumptions, we find for the first time that the standard ruler has a length of 103.9±2.3h⁻¹ Mpc. The value is a measurement, in contrast to the model-dependent theoretical prediction determined with model parameters set by Planck data (99.3±2.1h⁻¹ Mpc). The latter assumes the cold dark matter model with a cosmological constant, and that the ruler is the sound horizon at radiation drag. Adding passive galaxies as standard clocks or a local Hubble constant measurement allows the absolute BAO scale to be determined (142.8±3.7 Mpc), and in the former case the additional information makes the BAO length determination more precise (101.9±1.9h⁻¹ Mpc). The inverse curvature radius of the Universe is weakly constrained and consistent with zero, independently of the gravity model, provided it is metric. We find the effective number of relativistic species to be N(eff)=3.53±0.32, independent of late-time dark energy or gravity physics. PMID:25541763

  2. Stereoscopic Observation of Slipping Reconnection in a Double Candle-flame-shaped Solar Flare

    Science.gov (United States)

    Gou, Tingyu; Liu, Rui; Wang, Yuming; Liu, Kai; Zhuang, Bin; Chen, Jun; Zhang, Quanhao; Liu, Jiajia

    2016-04-01

    The 2011 January 28 M1.4 flare exhibits two side-by-side candle-flame-shaped flare loop systems underneath a larger cusp-shaped structure during the decay phase, as observed at the northwestern solar limb by the Solar Dynamics Observatory. The northern loop system brightens following the initiation of the flare within the southern loop system, but all three cusp-shaped structures are characterized by ∼10 MK temperatures, hotter than the arch-shaped loops underneath. The “Ahead” satellite of the Solar Terrestrial Relations Observatory provides a top view, in which the post-flare loops brighten sequentially, with one end fixed while the other apparently slipping eastward. By performing stereoscopic reconstruction of the post-flare loops in EUV and mapping out magnetic connectivities, we found that the footpoints of the post-flare loops are slipping along the footprint of a hyperbolic flux tube (HFT) separating the two loop systems and that the reconstructed loops share similarity with the magnetic field lines that are traced starting from the same HFT footprint, where the field lines are relatively flexible. These results argue strongly in favor of slipping magnetic reconnection at the HFT. The slipping reconnection was likely triggered by the flare and manifested as propagative dimmings before the loop slippage is observed. It may contribute to the late-phase peak in Fe xvi 33.5 nm, which is even higher than its main-phase counterpart, and may also play a role in the density and temperature asymmetry observed in the northern loop system through heat conduction.

  3. Stereoscopic Observation of Slipping Reconnection in a Double Candle-flame-shaped Solar Flare

    Science.gov (United States)

    Gou, Tingyu; Liu, Rui; Wang, Yuming; Liu, Kai; Zhuang, Bin; Chen, Jun; Zhang, Quanhao; Liu, Jiajia

    2016-04-01

    The 2011 January 28 M1.4 flare exhibits two side-by-side candle-flame-shaped flare loop systems underneath a larger cusp-shaped structure during the decay phase, as observed at the northwestern solar limb by the Solar Dynamics Observatory. The northern loop system brightens following the initiation of the flare within the southern loop system, but all three cusp-shaped structures are characterized by ˜10 MK temperatures, hotter than the arch-shaped loops underneath. The “Ahead” satellite of the Solar Terrestrial Relations Observatory provides a top view, in which the post-flare loops brighten sequentially, with one end fixed while the other apparently slipping eastward. By performing stereoscopic reconstruction of the post-flare loops in EUV and mapping out magnetic connectivities, we found that the footpoints of the post-flare loops are slipping along the footprint of a hyperbolic flux tube (HFT) separating the two loop systems and that the reconstructed loops share similarity with the magnetic field lines that are traced starting from the same HFT footprint, where the field lines are relatively flexible. These results argue strongly in favor of slipping magnetic reconnection at the HFT. The slipping reconnection was likely triggered by the flare and manifested as propagative dimmings before the loop slippage is observed. It may contribute to the late-phase peak in Fe xvi 33.5 nm, which is even higher than its main-phase counterpart, and may also play a role in the density and temperature asymmetry observed in the northern loop system through heat conduction.

  4. Improving NPT safeguards. Particularly at the natural uranium starting point

    International Nuclear Information System (INIS)

    According to the Non Proliferation Treaty (NPT) all nuclear material is subject to safeguards, but according to INFCIRC/153 the full range of safeguards is only applied beyond the 'starting point of safeguards', that is: The point at which nuclear material has reached a composition and purity suitable for fuel fabrication or enrichment. This paper addresses the two questions: (a) is the starting point adequately defined, and (b) what mesures could be applied to nuclear material before the starting point? Those questions have been asked before, some of the answers in this paper are new. (orig.)

  5. Optimal Gaussian Filter for Effective Noise Filtering

    OpenAIRE

    Kopparapu, Sunil; Satish, M

    2014-01-01

    In this paper we show that the knowledge of noise statistics contaminating a signal can be effectively used to choose an optimal Gaussian filter to eliminate noise. Very specifically, we show that the additive white Gaussian noise (AWGN) contaminating a signal can be filtered best by using a Gaussian filter of specific characteristics. The design of the Gaussian filter bears relationship with the noise statistics and also some basic information about the signal. We first derive a relationship...

  6. FY 2008 Next Generation Safeguards Initiative International Safeguards Education and Training Pilot Programs Summary Report

    International Nuclear Information System (INIS)

    Key component of the Next Generation Safeguards Initiative (NGSI) launched by the National Nuclear Security Administration is the development of human capital to meet present and future challenges to the safeguards regime. An effective university-level education in safeguards and related disciplines is an essential element in a layered strategy to rebuild the safeguards human resource capacity. Two pilot programs at university level, involving 44 students, were initiated and implemented in spring-summer 2008 and linked to hands-on internships at LANL or LLNL. During the internships, students worked on specific safeguards-related projects with a designated Laboratory Mentor to provide broader exposure to nuclear materials management and information analytical techniques. The Safeguards and Nuclear Material Management pilot program was a collaboration between the Texas A and M University (TAMU), Los Alamos National Laboratory (LANL) and Lawrence Livermore National Laboratory (LLNL). It included a 16-lecture course held during a summer internship program. The instructors for the course were from LANL together with TAMU faculty and LLNL experts. The LANL-based course was shared with the students spending their internship at LLNL via video conference. A week-long table-top (or hands-on) exercise on was also conducted at LANL. The student population was a mix of 28 students from a 12 universities participating in a variety of summer internship programs held at LANL and LLNL. A large portion of the students were TAMU students participating in the NGSI pilot. The International Nuclear Safeguards Policy and Information Analysis pilot program was implemented at the Monterey Institute for International Studies (MIIS) in cooperation with LLNL. It included a two-week intensive course consisting of 20 lectures and two exercises. MIIS, LLNL, and speakers from other U.S. national laboratories (LANL, BNL) delivered lectures for the audience of 16 students. The majority of students

  7. FY 2008 Next Generation Safeguards Initiative International Safeguards Education and Training Pilot Progerams Summary Report

    Energy Technology Data Exchange (ETDEWEB)

    Dreicer, M; Anzelon, G; Essner, J; Dougan, A; Doyle, J; Boyer, B; Hypes, P; Sokova, E; Wehling, F

    2008-10-17

    Key component of the Next Generation Safeguards Initiative (NGSI) launched by the National Nuclear Security Administration is the development of human capital to meet present and future challenges to the safeguards regime. An effective university-level education in safeguards and related disciplines is an essential element in a layered strategy to rebuild the safeguards human resource capacity. Two pilot programs at university level, involving 44 students, were initiated and implemented in spring-summer 2008 and linked to hands-on internships at LANL or LLNL. During the internships, students worked on specific safeguards-related projects with a designated Laboratory Mentor to provide broader exposure to nuclear materials management and information analytical techniques. The Safeguards and Nuclear Material Management pilot program was a collaboration between the Texas A&M University (TAMU), Los Alamos National Laboratory (LANL) and Lawrence Livermore National Laboratory (LLNL). It included a 16-lecture course held during a summer internship program. The instructors for the course were from LANL together with TAMU faculty and LLNL experts. The LANL-based course was shared with the students spending their internship at LLNL via video conference. A week-long table-top (or hands-on) exercise on was also conducted at LANL. The student population was a mix of 28 students from a 12 universities participating in a variety of summer internship programs held at LANL and LLNL. A large portion of the students were TAMU students participating in the NGSI pilot. The International Nuclear Safeguards Policy and Information Analysis pilot program was implemented at the Monterey Institute for International Studies (MIIS) in cooperation with LLNL. It included a two-week intensive course consisting of 20 lectures and two exercises. MIIS, LLNL, and speakers from other U.S. national laboratories (LANL, BNL) delivered lectures for the audience of 16 students. The majority of students were

  8. Miniaturized dielectric waveguide filters

    Science.gov (United States)

    Sandhu, Muhammad Y.; Hunter, Ian C.

    2016-10-01

    Design techniques for a new class of integrated monolithic high-permittivity ceramic waveguide filters are presented. These filters enable a size reduction of 50% compared to air-filled transverse electromagnetic filters with the same unloaded Q-factor. Designs for Chebyshev and asymmetric generalised Chebyshev filter and a diplexer are presented with experimental results for an 1800 MHz Chebyshev filter and a 1700 MHz generalised Chebyshev filter showing excellent agreement with theory.

  9. Fiscal Year 2014 Annual Report on BNLs Next Generation Safeguards Initiative Human Capital Development Activities

    Energy Technology Data Exchange (ETDEWEB)

    Pepper S. E.

    2014-10-10

    Brookhaven National Laboratory’s (BNL’s) Nonproliferation and National Security Department contributes to the National Nuclear Security Administration Office of Nonproliferation and International Security Next Generation Safeguards Initiative (NGSI) through university engagement, safeguards internships, safeguards courses, professional development, recruitment, and other activities aimed at ensuring the next generation of international safeguards professionals is adequately prepared to support the U.S. safeguards mission. This report is a summary of BNL s work under the NGSI program in Fiscal Year 2014.

  10. Panel on protection and management of plutonium: Subpanel on safeguards and security

    Energy Technology Data Exchange (ETDEWEB)

    Tape, J.W.

    1995-07-01

    Nuclear materials safeguards and security systems are described in the context of the nuclear nonproliferation regime. Materials of interest to safeguards, threats, proposals to strengthen International Atomic Energy Agency safeguards, evolving safeguards issues and requirements, system effectiveness, and elements of a global nuclear materials management regime are discussed. Safeguards are seen as an essential element of nuclear materials management, but not a driver for decisions regarding nuclear power or the disposal of excess weapon nuclear materials.

  11. Panel on protection and management of plutonium: Subpanel on safeguards and security

    International Nuclear Information System (INIS)

    Nuclear materials safeguards and security systems are described in the context of the nuclear nonproliferation regime. Materials of interest to safeguards, threats, proposals to strengthen International Atomic Energy Agency safeguards, evolving safeguards issues and requirements, system effectiveness, and elements of a global nuclear materials management regime are discussed. Safeguards are seen as an essential element of nuclear materials management, but not a driver for decisions regarding nuclear power or the disposal of excess weapon nuclear materials

  12. Reactor safeguards system assessment and design. Volume I

    Energy Technology Data Exchange (ETDEWEB)

    Varnado, G.B.; Ericson, D.M. Jr.; Daniel, S.L.; Bennett, H.A.; Hulme, B.L.

    1978-06-01

    This report describes the development and application of a methodology for evaluating the effectiveness of nuclear power reactor safeguards systems. Analytic techniques are used to identify the sabotage acts which could lead to release of radioactive material from a nuclear power plant, to determine the areas of a plant which must be protected to assure that significant release does not occur, to model the physical plant layout, and to evaluate the effectiveness of various safeguards systems. The methodology was used to identify those aspects of reactor safeguards systems which have the greatest effect on overall system performance and which, therefore, should be emphasized in the licensing process. With further refinements, the methodology can be used by the licensing reviewer to aid in assessing proposed or existing safeguards systems.

  13. Development of Pattern Recognition Options for Combining Safeguards Subsystems

    Energy Technology Data Exchange (ETDEWEB)

    Burr, Thomas L. [Los Alamos National Laboratory; Hamada, Michael S. [Los Alamos National Laboratory

    2012-08-24

    This talk reviews project progress in combining process monitoring data and nuclear material accounting data to improve the over nuclear safeguards system. Focus on 2 subsystems: (1) nuclear materials accounting (NMA); and (2) process monitoring (PM).

  14. Safety and safeguards aspects on retrievability: A German study

    International Nuclear Information System (INIS)

    The article refers shortly to the definition of the term 'retrievability' and shows two different possibilities of retrieval scenarios, their advantages and detriments. The second part lists the Safeguards aspects of retrievability, gives a short outlook on the present German Safeguards Reference Concept in the post-closure phase of a repository in a salt dome and about the results of German studies concerning some proposed Safeguards methods. Furthermore, Planned investigations on Safeguards in the post-closure phase of a repository are mentioned. The third and main part finally describes the results of the German Retrievability Study, which was elaborated in the middle of the nineties by DBE on behalf of the German Federal Ministry of Education, Science, Research and Technology, BMBF, under an R and D contract. (author)

  15. Authentication method for safeguards instruments securing data transmission

    International Nuclear Information System (INIS)

    Because of the worldwide increase in nuclear fuel cycle activities, the need arises to reduce inspection effort by increasing the inspection efficiency per facility. Therefore, more and more advanced safeguards instruments will be designed for automatic operation. In addition, sensoring and recording devices may be well separated from each other within the facility, while the data transmission medium is a cable. The basic problem is the authenticity of the transmitted information. It has to be ensured that no potential adversary is able to falsify the transmitted safeguards data, i.e. the data transmission is secured. At present, predominantly C/S-devices are designed for automatic and remote interrogation. Also in other areas of safeguards instrumentation authentication will become a major issue, in particular, where the facility operator may offer his process instrumentation to be used also for safeguards purposes. In this paper possibilities to solve the problem of authentication are analysed

  16. 75 FR 78777 - Advisory Committee On Reactor Safeguards; Renewal

    Science.gov (United States)

    2010-12-16

    ... From the Federal Register Online via the Government Publishing Office ] NUCLEAR REGULATORY COMMISSION Advisory Committee On Reactor Safeguards; Renewal AGENCY: U.S. Nuclear Regulatory Commission... accident phenomena; design of nuclear power plant structures, systems and components; materials...

  17. Implementation of the Safeguards System in the Republic of Tajikistan

    International Nuclear Information System (INIS)

    It is known that IAEA plays an important role in facilitation of nuclear non-proliferation as international authority which carries out nuclear inspections. Republic of Tajikistan in 1997 signed nuclear weapon non-proliferation treaty. Then in 2004 Safeguards agreement, additional protocol and small quantity protocol were signed. Information required in accordance with Safeguards agreement and Additional Protocol is figured on that IAEA could compile more detailed and exact conception about nuclear activity in Tajikistan and it has the following purpose: - Information will lead to more transparency, and make it possible to IAEA to ensure with high extent of confidence that in the framework of declared program, any unstated nuclear activity is concealed; - The more exact and comprehensive information, the rare is questions and discrepancies are originating; - Required information is the basis for effective planning and IAEA activity realization, related not only with safeguards implementation in regard to declared nuclear material but also ensuring of confidence in absence of undeclared nuclear activity in Tajikistan. Tajikistan provides necessary information to IAEA in accordance with Additional Protocol: Location where nuclear material is available or might be available; Information about all buildings where nuclear material could be available; Ready to provide assistance for IAEA missions on environmental sampling; Provides to IAEA inspectors multiple visas; Information about scientific and research works. Exclusive importance for IAEA safeguards agreement is high safeguards culture. IAEA should regularly conduct seminars on advanced assessment of safeguards culture - exactly as recommends to nuclear sites regularly to assess safety culture, and to undertake steps on elimination of any revealed shortcomings. One of the important safeguards criteria is nuclear knowledge preservation. IAEA member-states should advocate initiative on attraction and next generation

  18. Influence of safeguards and fire protection on criticality safety

    International Nuclear Information System (INIS)

    There are several positive influences of safeguards and fire protection on criticality safety. Experts in each discipline must be aware of regulations and requirements of the others and work together to ensure a fault-tree design. EG and G Idaho, Inc., routinely uses an Occupancy-Use Readiness Manual to consider all aspects of criticality safety, fire protection, and safeguards. The use of the analytical tree is described

  19. Virtual Reality based System for Nuclear Safeguards Applications

    OpenAIRE

    Goncalves, Joao; MOLTO CARACENA Teofilo; SEQUEIRA Vitor; Vendrell Vidal, Eduardo

    2010-01-01

    Many Nuclear Safeguards applications can benefit from interactive design and simulation tools to be used by planners and inspectors at headquarters. Virtual Reality technologies provide the capability to create accurate, realistic and immersive environments, as well as create ¿objects¿ ¿ representing equipment, measurement devices and radiation sources, with specific properties and behaviours. To be adapted to Safeguards, applications need to reflect the equipment, functions (including the la...

  20. Minor isotope measurements for safeguarding a uranium enrichment plant

    Energy Technology Data Exchange (ETDEWEB)

    Blumkin, S.; Levin, S.A.; Von Halle, E.

    1979-03-26

    A study of the behavior of the minor uranium isotopes in enrichment cascades indicates that the measurement of their concetrations in cascade feed and withdrawal streams can be used to confirm or deny material accountability results in safeguarding an enrichment plant. In further support of safeguard measures, an indirect non-intrusive method to measure cascade uranium inventory has been devised and tested satisfactorily in a gaseous diffusion cascade.

  1. Standing Advisory Group on Safeguards Implementation. A status report

    International Nuclear Information System (INIS)

    The implementation of IAEA safeguards is a subject which attracts the attention of virtually every IAEA Member State. The reasons for this attention are many and varied and although much has been said and written about the subject it is clear that there will be continuing debate. In the hope of establishing a forum for a systematic review of current and anticipated future safeguards implementation problems, in 1975 the Director General called together ten persons from Member States with nuclear programmes at varying stages of development to form the Standing Advisory Group on Safeguards Implementation. The Group was later expanded to twelve and changes were made in its membership from time to time. The Director General called upon the Group to: (1) Evaluate the technical objectives of IAEA safeguards, particularly with a view to ensuring their continued validity in the light of technical developments; (2) assess the effectiveness and efficiency of specific safeguards operating methods in meeting these technical objectives; (3) advise on techniques to be employed in safeguards operations in order to ensure that these techniques conform to the latest international standards; and (4) recommend areas where further work on methods and techniques is needed. This paper reviews the work of the Standing Advisory Group on Safeguards Implementation since its formation in 1975, summarizes the subjects that have been examined and the advice rendered, and outlines the problem areas requiring further study in the interest of maximizing the effectiveness and efficiency of safeguards within the technical, legal and financial constraints which are expected to apply. (author)

  2. A new Facility for NDA-Safeguards Training

    OpenAIRE

    HOLZLEITNER Ludwig; GALY Jean; Mayer, Klaus; KREVICA INDRA; ZSIGRAI JOZSEF; TOMA MAGDALENA

    2013-01-01

    On an initiative of the Joint Research Centre a European Nuclear Safety and Security School (EN3S) is being established. This School shall offer training on specialization topics related to the nuclear fuel cycle, one of it is "Nuclear Security, Safeguards and Forensics". For this reason the EUSECTRA project has been carried out at ITU in collaboration with DG-HOME. Its task is to build up training facilities and to offer training concerning nuclear security, safeguards and forensics to a wid...

  3. The role of neural networks in safeguards and security

    International Nuclear Information System (INIS)

    Interpreting data from nuclear safeguards and computer security systems is a tedious and time-consuming task. It typically requires the examination of large amounts of data for unusual patterns of activity. Neural networks provide a flexible pattern-recognition capability that can be adapted for these purposes. In this paper the author describes a methodology for performing anomaly detection and consistency checking in safeguards and security data

  4. Technology transfer - insider protection workshop (Safeguards Evaluation Method - Insider Threat)

    International Nuclear Information System (INIS)

    The Safeguards Evaluation Method - Insider Threat, developed by Lawrence Livermore National Laboratory, is a field-applicable tool to evaluate facility safeguards against theft or diversion of special nuclear material (SNM) by nonviolent insiders. To ensure successful transfer of this technology from the laboratory to DOE field offices and contractors, LLNL developed a three-part package. The package includes a workbook, user-friendly microcomputer software, and a three-day training program. The workbook guides an evaluation team through the Safeguards Evaluation Method and provides forms for gathering data. The microcomputer software assists in the evaluation of safeguards effectiveness. The software is designed for safeguards analysts with no previous computer experience. It runs on an IBM Personal Computer or any compatible machine. The three-day training program is called the Insider Protection Workshop. The workshop students learn how to use the workbook and the computer software to assess insider vulnerabilities and to evaluate the benefits and costs of potential improvements. These activities increase the students' appreciation of the insider threat. The workshop format is informal and interactive, employing four different instruction modes: classroom presentations, small-group sessions, a practical exercise, and ''hands-on'' analysis using microcomputers. This approach to technology transfer has been successful: over 100 safeguards planners and analysts have been trained in the method, and it is being used at facilities through the DOE complex

  5. Redefining interrelationship between nuclear safety, nuclear security and safeguards

    International Nuclear Information System (INIS)

    Since the beginning of this century, the so-called 3Ss (Nuclear Safety, Nuclear Security and Safeguards) have become major regulatory areas for peaceful uses of nuclear energy. In order to rationalize the allocation of regulatory resources, interrelationship of the 3Ss should be investigated. From the viewpoint of the number of the parties concerned in regulation, nuclear security is peculiar with having “aggressors” as the third party. From the viewpoint of final goal of regulation, nuclear security in general and safeguards share the goal of preventing non-peaceful uses of nuclear energy, though the goal of anti-sabotage within nuclear security is rather similar to nuclear safety. As often recognized, safeguards are representative of various policy tools for nuclear non-proliferation. Strictly speaking, it is not safeguards as a policy tool but nuclear non-proliferation as a policy purpose that should be parallel to other policy purposes (nuclear safety and nuclear security). That suggests “SSN” which stands for Safety, Security and Non-proliferation is a better abbreviation rather than 3Ss. Safeguards as a policy tool should be enumerated along with nuclear safety regulation, nuclear security measures and trade controls on nuclear-related items. Trade controls have been playing an important role for nuclear non-proliferation. These policy tools can be called “SSST” in which Trade controls are also emphasized along with Safety regulation, Security measures and Safeguards. (author)

  6. Global partnering related to nuclear materials safeguards and security - A pragmatic approach to international safeguards work

    International Nuclear Information System (INIS)

    This paper documents issues Nuclear Fuel Services, Inc. has addressed in the performance of international work to safeguards and security work. It begins with a description of the package we put together for a sample proposal for the Global Threat Reduction Initiative, for which we were ranked number one for technical approach and cost, and concludes with a discussion of approaches that we have taken to performing this work, including issues related to performing the work as part of a team. The primary focus is on communication, workforce, equipment, and coordination issues. Finally, the paper documents the rules that we use to assure the work is performed safely and successfully. (author)

  7. Active Optical Lattice Filters

    OpenAIRE

    Gary Evans; MacFarlane, Duncan L.; Govind Kannan; Jian Tong; Issa Panahi; Vishnupriya Govindan; L. Roberts Hunt

    2005-01-01

    Optical lattice filter structures including gains are introduced and analyzed. The photonic realization of the active, adaptive lattice filter is described. The algorithms which map between gains space and filter coefficients space are presented and studied. The sensitivities of filter parameters with respect to gains are derived and calculated. An example which is relevant to adaptive signal processing is also provided.

  8. Supporting Technical Work Under IAEA Safeguards Agreements of 2013 Completed by Laboratory of Technical Research for Nuclear Safeguards

    Institute of Scientific and Technical Information of China (English)

    GAO; Qiang; LIU; Hong-bin; YANG; Qun; BU; Li-xin; MIAO; Qiang; HE; Li-xia; XU; Zheng; ZHANG; Wen-liang

    2013-01-01

    Safeguards applied by the International Atomic Energy Agency(IAEA)are an important element of the global nuclear non-proliferation regime.In order to verify that commitments made by states under safeguards agreements with the IAEA are fulfilled.China signed the voluntary offer agreement(INFCIRC/369)with IAEA in 1988.The agreement entered into force in 1989.There are three nuclear

  9. Corporate strategic plan for safeguards and security

    International Nuclear Information System (INIS)

    Department of Energy (DOE) safeguards and security (S and S) is a team effort, consisting of Field, National Laboratories, Program Office, and Headquarters units cooperating to support the Department's diverse security needs. As an integral part of the nation's security structure, the DOE S and S Program regularly supports and works in cooperation with other US Government agencies and private industry to improve the national security posture. Thus, inter- and intra-agency partnerships play an invaluable role in the continuing efforts to integrate and implement improved ways of doing business. Their Corporate Strategic Plan provides a road map to guide, track, and provide feedback for the incorporation and implementation of S and S activities within DOE. Part 1 Planning Framework, describes those overarching factors which influence the planning endeavors. Part 2, Strategic Perspective, outlines where the S and S Program has been and how they will move to the future through core competencies, changing cultural thinking, and implementing their strategies. Part 3, Strategic and Operational Integration, details critical focus areas, strategies, and success indicators designed to enhance inter-agency S and S integration and promote cooperation with external agencies. This Plan will be reviewed annually to ensure it remains supportive and fully-engaged with the nation's and international security environments

  10. SALE: Safeguards Analytical Laboratory Evaluation computer code

    Energy Technology Data Exchange (ETDEWEB)

    Carroll, D.J.; Bush, W.J.; Dolan, C.A.

    1976-09-01

    The Safeguards Analytical Laboratory Evaluation (SALE) program implements an industry-wide quality control and evaluation system aimed at identifying and reducing analytical chemical measurement errors. Samples of well-characterized materials are distributed to laboratory participants at periodic intervals for determination of uranium or plutonium concentration and isotopic distributions. The results of these determinations are statistically-evaluated, and each participant is informed of the accuracy and precision of his results in a timely manner. The SALE computer code which produces the report is designed to facilitate rapid transmission of this information in order that meaningful quality control will be provided. Various statistical techniques comprise the output of the SALE computer code. Assuming an unbalanced nested design, an analysis of variance is performed in subroutine NEST resulting in a test of significance for time and analyst effects. A trend test is performed in subroutine TREND. Microfilm plots are obtained from subroutine CUMPLT. Within-laboratory standard deviations are calculated in the main program or subroutine VAREST, and between-laboratory standard deviations are calculated in SBLV. Other statistical tests are also performed. Up to 1,500 pieces of data for each nuclear material sampled by 75 (or fewer) laboratories may be analyzed with this code. The input deck necessary to run the program is shown, and input parameters are discussed in detail. Printed output and microfilm plot output are described. Output from a typical SALE run is included as a sample problem.

  11. Use of Antineutrino Detectors for Nuclear Reactor Safeguards Effectiveness Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Bernstein, A; Lambert, H E; Elayat, H A; O' Connell, W J; Rexroth, P; Baldwin, G; Bowden, N; Huelskamp, R

    2006-06-05

    As described in an earlier article [1], important information regarding reactor power and the amount and type of fissile material in reactor cores can be determined by measuring the antineutrino rate and energy spectrum, using a cubic meter scale antineutrino detector at tens of meters standoff from the core. Current International Atomic Energy Agency (IAEA) safeguards techniques do not provide such real-time quantitative information regarding core power levels and isotopic composition. The possible benefits of this approach are several and have been discussed in the earlier article. One key advantage is that the method gives the inspecting agency completely independent access to real-time information on the operational status and fissile content of the core. Furthermore, the unattended and non-intrusive nature of the technology may reduce the monitoring burden on the plant operator, even though more information is being provided than is available within the current IAEA safeguards regime. Here we present a detailed analytical framework for measuring the impact that such a detector might have on IAEA safeguards, if implemented. To perform the analysis, we will use initial data from our operating detector and a standard analysis technique for safeguards regimes, developed at Lawrence Livermore National Laboratory. Because characterization of the prototype detector is still underway, and because improvements in the prototype could have important impact on safeguards performance, the results presented here should be understood to be preliminary, and not reflective of the ultimate performance of the system. The structure of this paper is as follows. Reactor safeguards and the relevant properties of antineutrino detectors are briefly reviewed. A set of hypothetical diversion scenarios are then described, and one of these is analyzed using the Lawrence Livermore National Laboratory Integrated Safeguards System Analysis Tool (LISSAT) The probability of successful

  12. Lessons Learned in International Safeguards - Implementation of Safeguards at the Rokkasho Reprocessing Plant

    Energy Technology Data Exchange (ETDEWEB)

    Ehinger, Michael H [ORNL; Johnson, Shirley [Tucker Creek Consulting

    2010-02-01

    The focus of this report is lessons learned at the Rokkasho Reprocessing Plant (RRP). However, the subject of lessons learned for application of international safeguards at reprocessing plants includes a cumulative history of inspections starting at the West Valley (New York, U.S.A.) reprocessing plant in 1969 and proceeding through all of the efforts over the years. The RRP is the latest and most challenging application the International Atomic Energy Agency has faced. In many ways the challenges have remained the same, timely inspection and evaluation with limited inspector resources, with the continuing realization that planning and preparations can never start early enough in the life cycle of a facility. Lessons learned over the years have involved the challenges of using ongoing advances in technology and dealing with facilities with increased throughput and continuous operation. This report will begin with a review of historical developments and lessons learned. This will provide a basis for a discussion of the experiences and lessons learned from the implementation of international safeguards at RRP.

  13. Study on Lavender Fragrance Used in Candles%薰衣草香精在蜡烛中的应用研究

    Institute of Scientific and Technical Information of China (English)

    潘利君; 汪涓涓

    2011-01-01

    以三种不同风格的薰衣草香精为例,探讨了香精在蜡烛中的应用.对不同加香量的蜡烛,分别进行熔点测试、紫外线测试、低温测试和燃烧测试.对实验现象和结果进行了分析,总结了影响加香蜡烛质量稳定性的因素,为国内同行进行生产和相关研究提供参考.%Three different types of lavender fragrance for candles had been prepared for the test. The characteristics of the flavor candles had been determined, which included melting point, color of the candles after UV irradiated, frozen and burning results. Some factors that may affect the quality and stability of flavor candles had been discussed for references.

  14. "It Is Better to Light a Candle than to Curse the Darkness": Ethel Thompson Overby and Democratic Schooling in Richmond, Virginia, 1910-1958

    Science.gov (United States)

    Ward Randolph, Adah L.

    2012-01-01

    In 1933, Ethel Thompson Overby became the first African American female principal in Richmond, Virginia. Her motto was "It is better to light a candle than to curse the darkness" (Overby 1975, 1). Before becoming principal, Overby had been a teacher in the southern urban "de jure" segregated schools of the city. How did the racially segregated…

  15. Filter synthesis using Genesys S/Filter

    CERN Document Server

    Rhea, Randall W

    2014-01-01

    S/Filter includes tools beyond direct synthesis, including a wide variety of both exact and approximate equivalent network transforms, methods for selecting the most desirable out of potentially thousands of synthesized alternatives, and a transform history record that simplifies design attempts requiring iteration. Very few software programs are based on direct synthesis, and the additional features of S/Filter make it a uniquely effective tool for filter design.This resource presents a practical guide to using Genesys software for microwave and RF filter design and synthesis. The focus of th

  16. IAEA safeguards under the non-proliferation treaty

    International Nuclear Information System (INIS)

    The conventional safeguards system of the IAEA depends strongly on nuclear material accountancy. It is based on the concept that as long as all nuclear weapon-usable material is accounted for and verified to be in peaceful activities, the world can be confident that it is not used to produce nuclear explosive devices. Since weapon-usable nuclear material is essential for any such device, a tight material control was considered to be sufficient to verify non-proliferation. As a result of Iraq, the safeguards community began to seriously re-think some fundamental tenets of safeguards. Since the Summer of 1993, the IAEA has vigorously pursued a program of development aimed at strengthening its safeguards, the so-called 'Program 93+2'. In its meeting of March 1995, just prior to the NPT Conference in New York, the Board of Governors of the IAEA has reiterated that the purpose of comprehensive safeguards agreements is to verify that nuclear materials are not diverted. The verification should provide a credible assurance of the non-diversion of nuclear material from declared activities and the absence of undeclared nuclear activities. The Board recognized that a strengthened safeguards system will benefit from technological development and will call for greater access to relevant information and greater physical access to relevant sites. As far as clandestine activities are concerned, one technical area that appears particularly interesting is the application of environmental sampling for safeguards purposes. These methods allow for chemical and isotopic analysis of minute samples (as small as 10-15 g) which may be collected within declared facilities or away from nuclear facilities, e.g., water, soil and biota samples, that might provide indications of clandestine activity. This method has been and will continue to be used in Iraq. Several Member States have offered their assistance in the conduct of environmental monitoring field trials and related technical areas

  17. Activities of the ESARDA Working Group on Integrated Safeguards

    International Nuclear Information System (INIS)

    Full text: ESARDA, the European Safeguards Research and Development Association, pursues as a main objective to assist the European safeguards community with advancing progress in safeguards and enhancing the efficiency of systems and measures. Key bodies of ESARDA are standing Working Groups dealing with various technical subjects. The ESARDA Working Group on Integrated Safeguards was created in 2000 with the objective to provide the Safeguards Community with expert advice on methodologies and approaches to integrate INFCIRC/153 and INFCIRC/540 measures and to present a forum for the exchange of information, views and experiences in that regard. Its members represent inspectorates, national authorities, operators and research centres active in the field of safeguards. The Working Group very soon realized that a first milestone on the road to Integrated Safeguards is the successful and functional implementation of the Additional Protocol. Discussions and activities concentrated on actions necessary to reach this end thereby taking into account the specific situation in European States. Among the topics discussed were issues of: - how to establish a functional site definition for different types of installations, ranging from small locations with very small amounts of nuclear material to complex installations with a complex history; - how to deal with different and even conflicting requirements in the context of unannounced inspections; and - how to interpret and handle the requirements for R and D declarations considering the needs and interests of all parties involved; etc. The IAEA participated in most of the meetings as an observer and provided the group with valuable background information on Additional Protocol questions and received in turn a deep insight into our considerations, motivations and concerns. This procedure contributed much to a better mutual understanding that is not least reflected in the revised draft of the AP implementation guidelines

  18. Implementation of integrated safeguards at nuclear fuel plant Pitesti Romania

    Energy Technology Data Exchange (ETDEWEB)

    Olaru, Vasilica; Tiberiu, Ivana; Epure, Gheorghe [Nuclear Safety Department, Nuclear Fuel Plant Pitesti, Cimpului, No 1, 115400 Mioveni (Romania)

    2010-07-01

    The nuclear activity in Romania was for many years under Traditional Safeguards (TS) and has developed in good conditions this type of nuclear safeguards. Now it has the opportunity to improve the performance and quality of the safeguards activity and increase the accountancy and control of nuclear material by passing to Integrated Safeguards (IS). The legal framework is Law 100/2000 for ratification of the Protocol between Romania and International Atomic Energy Agency (IAEA), additional to the Agreement between the Socialist Republic of Romania Government and IAEA related to safeguards as part of the Treaty on the non-proliferation of nuclear weapons published in the Official Gazette no. 3/31 January 1970, and the Additional Protocol content published in the Official Gazette no. 295/ 29.06.2000. The first discussion about Integrated Safeguards (IS) between Nuclear Fuel Plant (FCN) representatives and IAEA inspectors was in June 2005. In Feb. 2007 an IAEA mission visited FCN and established the main steps for implementing the IS. There were visited the storages, technological flow, and was reviewed the residence times for different nuclear materials, the applied chemical analysis, metrological methods, weighting method and elaborating the documents and lists. At that time the IAEA and FCN representatives established the main points for starting the IS at FCN: perform the Short Notice Random Inspections (SNRI), communicate the eligible days for SNRI for each year, communicate the estimated deliveries and shipments for first quarter and then for the rest of the year, daily mail box declaration (DD) with respect to the residence time for several nuclear material, advance notification (AN) for each nuclear material transfer (shipments and receipts), others. At 01 June 2007 Romania has passed officially to Integrated Safeguards and FCN (RO-D) has taken all measures to realize this objective. (authors)

  19. Safeguard monitoring of direct electrolytic reduction

    Science.gov (United States)

    Jurovitzki, Abraham L.

    Nuclear power is regaining global prominence as a sustainable energy source as the world faces the consequences of depending on limited fossil based, CO2 emitting fuels. A key component to achieving this sustainability is to implement a closed nuclear fuel cycle. Without achieving this goal, a relatively small fraction of the energy value in nuclear fuel is actually utilized. This involves recycling of spent nuclear fuel (SNF)---separating fissile actinides from waste products and using them to fabricate fresh fuel. Pyroprocessing is a viable option being developed for this purpose with a host of benefits compared to other recycling options, such as PUREX. Notably, pyroprocessing is ill suited to separate pure plutonium from spent fuel and thus has non-proliferation benefits. Pyroprocessing involves high temperature electrochemical and chemical processing of SNF in a molten salt electrolyte. During this batch process, several intermediate and final streams are produced that contain radioactive material. While pyroprocessing is ineffective at separating pure plutonium, there are various process misuse scenarios that could result in diversion of impure plutonium into one or more of these streams. This is a proliferation risk that should be addressed with innovative safeguards technology. One approach to meeting this challenge is to develop real time monitoring techniques that can be implemented in the hot cells and coupled with the various unit operations involved with pyroprocessing. Current state of the art monitoring techniques involve external chemical assaying which requires sample removal from these unit operations. These methods do not meet International Atomic Energy Agency's (IAEA) timeliness requirements. In this work, a number of monitoring techniques were assessed for their viability as online monitoring tools. A hypothetical diversion scenario for the direct electrolytic reduction process was experimentally verified (using Nd2O3 as a surrogate for PuO2

  20. ALOS satellite imagery utilization for safeguards

    International Nuclear Information System (INIS)

    This paper introduces examples of satellite imageries analysis and utilizations for safeguards activities. Recently, many kinds of satellite imageries are available in the world i.e., high-spatial resolution, multi- and hyper-spectral, multi-function, and multi-polarization radars. The problem is that how to obtain the required information from these digital images. The Japan Aerospace Exploration Agency (JAXA) has successfully launched the Advanced Land Observing Satellite (ALOS, nicknamed 'Daichi') on 24 January, 2006. The mission objectives are cartography, regional observation, disaster monitoring etc. ALOS has three instruments, PRISM, AVNIR-2, and PALSAR, to achieve these objectives. The ALOS research program can be categorized into two main parts of the ALOS mission: calibration and validation (Cal/Val), and application and science. We are presently carrying out the initial calibration and validation works for each instrument. It is very important to improve the absolute accuracy and image quality of the products. We establish and organize the international ALOS Cal/Val and science team (CVST) to do these works effectively. Based on the CVST activities, we are setting test sites and reference facilities in the world, and considering mission operation plans of each instrument to observe the test sites. The application and scientific results will demonstrate the ALOS data utilization capability. We define the digital surface model (DSM), ortho-rectified images for each sensor, and the surface deformation map as high-level and research products. In particular, geographical information such as elevation, topography, land use and land cover maps are necessary as basic information in many fields of practical applications and research areas. This paper describes our research and scientific activities including some preliminary results of calibration and validation, and examples of acquired images and high-level products related to geographical information. (author)