WorldWideScience

Sample records for safeguards performance model

  1. Towards unified performance measures for evaluating nuclear safeguard systems: mathematical foundations and formal comparison of existing models

    International Nuclear Information System (INIS)

    Corynen, G.C.

    1979-01-01

    An important step in the analysis of large-scale systems is the development of economical and meaningful measures of system performance. In the literature on analysis of nuclear safeguard systems, many performance measures have been advanced, but their interrelationships and their relevance to overall system objectives have not received attention commensurate with the effort spent in developing detailed safeguard models. The work reported here is an attempt to improve the development and evaluation of performance measures for nuclear safeguard systems. This work falls into three main areas. First, we develop a new framework which provides an initial basis for defining and structuring performance measures. To demonstrate that this framework allows a clear understanding of the purposes of nuclear safeguard systems, we employ it to state various safeguard questions clearly and concisely. The framework reflects the rough subsystem structure of safeguard systems - the detection and response subsystems - and formally accommodates various safeguard models. We especially emphasize two of these models which are under development at Lawrence Livermore Laboratory, the structured assessment approach (SAA) and the systems vulnerability assessment method (SVAM). Second, we examine some performance measures presently used in the nuclear safeguards area and in reliability theory in general. Some of these we accept and modify to obtain system performance measures that are an additive combination of subsystem performance measures, a very convenient form indeed. Others we reject as impractical and meaningless. Finally, we determine some common features between the SAA and SVAM models by formally comparing these models in our framework

  2. Coupling a transient solvent extraction module with the separations and safeguards performance model.

    Energy Technology Data Exchange (ETDEWEB)

    DePaoli, David W. (Oak Ridge National Laboratory, Oak Ridge, TN); Birdwell, Joseph F. (Oak Ridge National Laboratory, Oak Ridge, TN); Gauld, Ian C. (Oak Ridge National Laboratory, Oak Ridge, TN); Cipiti, Benjamin B.; de Almeida, Valmor F. (Oak Ridge National Laboratory, Oak Ridge, TN)

    2009-10-01

    A number of codes have been developed in the past for safeguards analysis, but many are dated, and no single code is able to cover all aspects of materials accountancy, process monitoring, and diversion scenario analysis. The purpose of this work was to integrate a transient solvent extraction simulation module 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 SSPM was designed for materials accountancy and process monitoring analyses, but previous versions of the code have included limited detail on the chemical processes, including chemical separations. The transient solvent extraction model is based on the ORNL SEPHIS code approach to consider solute build up in a bank of contactors in the PUREX process. Combined, these capabilities yield a more robust transient separations and safeguards model for evaluating safeguards system design. This coupling and initial results are presented. In addition, some observations toward further enhancement of separations and safeguards modeling based on this effort are provided, including: items to be addressed in integrating legacy codes, additional improvements needed for a fully functional solvent extraction module, and recommendations for future integration of other chemical process modules.

  3. Coupling a Transient Solvent Extraction Module with the Separations and Safeguards Performance Model

    Energy Technology Data Exchange (ETDEWEB)

    de Almeida, Valmor F [ORNL; Birdwell Jr, Joseph F [ORNL; DePaoli, David W [ORNL; Gauld, Ian C [ORNL

    2009-10-01

    A past difficulty in safeguards design for reprocessing plants is that no code existed for analysis and evaluation of the design. A number of codes have been developed in the past, but many are dated, and no single code is able to cover all aspects of materials accountancy, process monitoring, and diversion scenario analysis. The purpose of this work was to integrate a transient solvent extraction simulation module developed at Oak Ridge National Laboratory, with the SSPM Separations and Safeguards Performance Model, developed at Sandia National Laboratory, as a first step toward creating a more versatile design and evaluation tool. The SSPM was designed for materials accountancy and process monitoring analyses, but previous versions of the code have included limited detail on the chemical processes, including chemical separations. The transient solvent extraction model is based on the ORNL SEPHIS code approach to consider solute build up in a bank of contactors in the PUREX process. Combined, these capabilities yield a much more robust transient separations and safeguards model for evaluating safeguards system design. This coupling and the initial results are presented. In addition, some observations toward further enhancement of separations and safeguards modeling based on this effort are provided, including: items to be addressed in integrating legacy codes, additional improvements needed for a fully functional solvent extraction module, and recommendations for future integration of other chemical process modules.

  4. Modeling and Simulation for Safeguards

    International Nuclear Information System (INIS)

    Swinhoe, Martyn T.

    2012-01-01

    The purpose of this talk is to give an overview of the role of modeling and simulation in Safeguards R and D and introduce you to (some of) the tools used. Some definitions are: (1) Modeling - the representation, often mathematical, of a process, concept, or operation of a system, often implemented by a computer program; (2) Simulation - the representation of the behavior or characteristics of one system through the use of another system, especially a computer program designed for the purpose; and (3) Safeguards - the timely detection of diversion of significant quantities of nuclear material. The role of modeling and simulation are: (1) Calculate amounts of material (plant modeling); (2) Calculate signatures of nuclear material etc. (source terms); and (3) Detector performance (radiation transport and detection). Plant modeling software (e.g. FACSIM) gives the flows and amount of material stored at all parts of the process. In safeguards this allow us to calculate the expected uncertainty of the mass and evaluate the expected MUF. We can determine the measurement accuracy required to achieve a certain performance.

  5. State-wide performance criteria for international safeguards

    International Nuclear Information System (INIS)

    Budlong-Sylvester, K.W.; Pilat, Joseph F.; Stanbro, W.D.

    2001-01-01

    Traditionally, the International Atomic Energy Agency (IAEA) has relied upon prescriptive criteria to guide safeguards implementation. The prospect of replacing prescriptive safeguards criteria with more flexible performance criteria would constitute a structural change in safeguards and raises several important questions. Performance criteria imply that while safeguards goals will be fixed, the means of attaining those goals will not be explicitly prescribed. What would the performance objectives be under such a system? How would they be formulated? How would performance be linked to higher level safeguards objectives? How would safeguards performance be measured State-wide? The implementation of safeguards under performance criteria would also signal a dramatic change in the manner the Agency does business. A higher degree of flexibility could, in principle, produce greater effectiveness and efficiency, but would come with a need for increased Agency responsibility in practice. To the extent that reliance on prescriptive criteria decreases, the burden of justifying actions and ensuring their transparency will rise. Would there need to be limits to safeguards implementation? What would be the basis for setting such limits? This paper addresses these and other issues and questions relating to both the formulation and the implementation of performance-based criteria.

  6. Safeguards First Principle Initiative (SFPI) Cost Model

    International Nuclear Information System (INIS)

    Price, Mary Alice

    2010-01-01

    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.

  7. 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.

  8. Nuclear facility safeguards systems modeling using discrete event simulation

    International Nuclear Information System (INIS)

    Engi, D.

    1977-01-01

    The threat of theft or dispersal of special nuclear material at a nuclear facility is treated by studying the temporal relationships between adversaries having authorized access to the facility (insiders) and safeguards system events by using a GASP IV discrete event simulation. The safeguards system events--detection, assessment, delay, communications, and neutralization--are modeled for the general insider adversary strategy which includes degradation of the safeguards system elements followed by an attempt to steal or disperse special nuclear material. The performance measure used in the analysis is the estimated probability of safeguards system success in countering the adversary based upon a predetermined set of adversary actions. An exemplary problem which includes generated results is presented for a hypothetical nuclear facility. The results illustrate representative information that could be utilized by safeguards decision-makers

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

    International Nuclear Information System (INIS)

    Boozer, D.D.; Engi, D.

    1977-11-01

    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

  10. An integrated approach to validation of safeguards and security program performance

    International Nuclear Information System (INIS)

    Altman, W.D.; Hunt, J.S.; Hockert, J.W.

    1988-01-01

    Department of Energy (DOE) requirements for safeguards and security programs are becoming increasingly performance oriented. Master Safeguards and Security Agreemtns specify performance levels for systems protecting DOE security interests. In order to measure and validate security system performance, Lawrence Livermore National Laboratory (LLNL) has developed cost effective validation tools and a comprehensive validation approach that synthesizes information gained from different activities such as force on force exercises, limited scope performance tests, equipment testing, vulnerability analyses, and computer modeling; into an overall assessment of the performance of the protection system. The analytic approach employs logic diagrams adapted from the fault and event trees used in probabilistic risk assessment. The synthesis of the results from the various validation activities is accomplished using a method developed by LLNL, based upon Bayes' theorem

  11. Safeguards and security modeling for electrochemical plants

    International Nuclear Information System (INIS)

    Cipiti, B.B.; Duran, F.A.; Mendoza, L.A.; Parks, M.J.; Dominguez, D.; Le, T.D.

    2013-01-01

    Safeguards and security design for reprocessing plants can lead to excessive costs if not incorporated early in the design process. The design for electrochemical plants is somewhat uncertain since these plants have not been built at a commercial scale in the past. The Separation and Safeguards Performance Model (SSPM), developed at Sandia National Laboratories, has been used for safeguards design and evaluation for multiple reprocessing plant types. The SSPM includes the following capabilities: -) spent fuel source term library, -) mass tracking of elements 1-99 and bulk solid/liquids, -) tracking of heat load and activity, -) customisable measurement points, -) automated calculation of ID and error propagation, -) alarm conditions and statistical tests, and -) user-defined diversion scenarios. Materials accountancy and process monitoring data can provide more timely detection of material loss specifically to protect against the insider threat. While the SSPM is capable of determining detection probabilities and examining detection times for material loss scenarios, it does not model the operations or spatial effects for a plant design. The STAGE software was chosen to model the physical protection system. STAGE provides a framework to create end-to-end scalable force-on-force combat simulations. It allows for a complete 3D model of a facility to be designed along with the design of physical protection elements. This software, then, can be used to model operations and response for various material loss scenarios. The future integration of the SSPM model data with the STAGE software will provide a more complete analysis of diversion scenarios to assist plant designers

  12. Safeguards and security modeling for electrochemical plants

    Energy Technology Data Exchange (ETDEWEB)

    Cipiti, B.B.; Duran, F.A.; Mendoza, L.A.; Parks, M.J.; Dominguez, D.; Le, T.D. [Sandia National Laboratories, PO Box 5800 MS 0747, Albuquerque, NM 87185 (United States)

    2013-07-01

    Safeguards and security design for reprocessing plants can lead to excessive costs if not incorporated early in the design process. The design for electrochemical plants is somewhat uncertain since these plants have not been built at a commercial scale in the past. The Separation and Safeguards Performance Model (SSPM), developed at Sandia National Laboratories, has been used for safeguards design and evaluation for multiple reprocessing plant types. The SSPM includes the following capabilities: -) spent fuel source term library, -) mass tracking of elements 1-99 and bulk solid/liquids, -) tracking of heat load and activity, -) customisable measurement points, -) automated calculation of ID and error propagation, -) alarm conditions and statistical tests, and -) user-defined diversion scenarios. Materials accountancy and process monitoring data can provide more timely detection of material loss specifically to protect against the insider threat. While the SSPM is capable of determining detection probabilities and examining detection times for material loss scenarios, it does not model the operations or spatial effects for a plant design. The STAGE software was chosen to model the physical protection system. STAGE provides a framework to create end-to-end scalable force-on-force combat simulations. It allows for a complete 3D model of a facility to be designed along with the design of physical protection elements. This software, then, can be used to model operations and response for various material loss scenarios. The future integration of the SSPM model data with the STAGE software will provide a more complete analysis of diversion scenarios to assist plant designers.

  13. Modeling and simulation for process and safeguards system design

    International Nuclear Information System (INIS)

    Gutmacher, R.G.; Kern, E.A.; Duncan, D.R.; Benecke, M.W.

    1983-01-01

    A computer modeling and simulation approach that meets the needs of both the process and safeguards system designers is described. The results have been useful to Westinghouse Hanford Company process designers in optimizing the process scenario and operating scheme of the Secure Automated Fabrication line. The combined process/measurements model will serve as the basis for design of the safeguards system. Integration of the process design and the safeguards system design should result in a smoothly operating process that is easier to safeguard

  14. 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.

  15. Simulation of personnel control systems with the Insider Safeguards Effectiveness Model (ISEM)

    International Nuclear Information System (INIS)

    Boozer, D.D.; Engi, D.

    1977-04-01

    Nuclear safeguards systems are being designed to prevent theft or sabotage of radioactive material by persons employed in nuclear facilities. As incidents of terrorism have increased, the need for more advanced safeguards systems has been recognized. Dynamic simulation models have been found useful in determining relative safeguards system effectiveness. A simulation model which treats certain aspects of the insider problem is the Insider Safeguards Effectiveness Model (ISEM). This report describes the model, discusses its role in analysis and design of safeguards systems, and explains the use of the model in conjunction with other models used for safeguards system design. Effectiveness results and sensitivities to safeguard system parameter variations are reported, and a comprehensive example of ISEM use for a hypothetical facility is given

  16. Simulation of personnel control systems with the Insider Safeguards Effectiveness Model (ISEM)

    Energy Technology Data Exchange (ETDEWEB)

    Boozer, D.D.; Engi, D.

    1977-04-01

    Nuclear safeguards systems are being designed to prevent theft or sabotage of radioactive material by persons employed in nuclear facilities. As incidents of terrorism have increased, the need for more advanced safeguards systems has been recognized. Dynamic simulation models have been found useful in determining relative safeguards system effectiveness. A simulation model which treats certain aspects of the insider problem is the Insider Safeguards Effectiveness Model (ISEM). This report describes the model, discusses its role in analysis and design of safeguards systems, and explains the use of the model in conjunction with other models used for safeguards system design. Effectiveness results and sensitivities to safeguard system parameter variations are reported, and a comprehensive example of ISEM use for a hypothetical facility is given.

  17. Nuclear safeguards surveys as performed by the Albuquerque operations office

    International Nuclear Information System (INIS)

    Jewell, D.

    1987-01-01

    The nuclear safeguards survey program as administered by the Albuquerque Operations Office (AL) is comprehensive in scope and evaluates the facility's safeguards program for an entire appraisal period. The survey program focuses on both the integrated and graded safeguards concepts and includes both compliance and performance evaluations. The program utilizes independent measurement support to verify facility inventory values and measurement system capabilities. The AL survey program is oriented towards facility development and management as opposed to development and management by numerous detailed departmental directives

  18. 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.

  19. Methodology and preliminary models for analyzing nuclear safeguards decisions

    International Nuclear Information System (INIS)

    1978-11-01

    This report describes a general analytical tool designed to assist the NRC 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

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

    International Nuclear Information System (INIS)

    Judd, B.R.; Weissenberger, S.

    1978-11-01

    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

  1. Safeguards in Pyroprocessing: an Integrated Model Development and Measurement Data Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Zhang, Jinsuo [The Ohio State Univ., Columbus, OH (United States). Nuclear Engineering Program, Dept. of Mechanical and Aerospace Engineering

    2017-10-01

    Pyroprocessing is an electrochemical method based on the molten salt electrolyte, mainly the LiCl-KCl eutectic molten salt, to recycle the used nuclear fuel. For a conceptual design of commercial pyroprocessing facility, tons of special nuclear materials, namely U and Pu, may be involved, which could be used for non-peaceful purposes if they are diverted. Effective safeguards approaches have to be developed prior to the development and construction of a pyroprocessing facility. Present research focused on two main objectives, namely calculating the properties of nuclear species in LiCl-KCl molten salt and developing integrated model to safeguard a pyroprocessing facility. Understanding the characteristics of special nuclear materials in LiCl-KCl eutectic salt is extremely important to understand their behaviors in an electrorefiner. The model development for the separation processes in the pyroprocessing, including electrorefining, actinide drawdown, and rare earth drawdown benefits the understanding of material transport and separation performance of these processes under various conditions. The output signals, such as potential, current, and species concentration contribute to the material balance closure and provide safeguards signatures to detect the scenarios of diversion. U and Pu are the two main elements concerned in this study due to our interest in safeguards.

  2. Safeguards approach for conditioning facility for spent fuel

    International Nuclear Information System (INIS)

    Younkin, J.M.; Barham, M.; Moran, B.W.

    1999-01-01

    A safeguards approach has been developed for conditioning facilities associated with the final disposal of spent fuel in geologic repositories. The proposed approach is based on a generic conditioning facility incorporating common features of conditioning facility designs currently proposed. The generic facility includes a hot cell for consolidation of spent fuel pins and repackaging of spent fuel items such as assemblies and cans of pins. The consolidation process introduces safeguards concerns which have not previously been addressed in traditional safeguards approaches. In developing the safeguards approach, diversion of spent fuel was assessed in terms of potential target items, operational activities performed on the items, containment of the items, and concealment activities performed on the items. The combination of these factors defines the potential diversion pathways. Diversion pathways were identified for spent fuel pellets, pins, assemblies, canisters, and casks. Diversion activities provide for opportunities of detection along the diversion paths. Potential detection methods were identified at several levels of diversion activities. Detection methods can be implemented through safeguards measures. Safeguards measures were proposed for each of the primary safeguards techniques of design information verification (DIV), containment and surveillance (C/S), and material accountancy. Potential safeguards approaches were developed by selection of appropriate combinations of safeguards measures. For all candidate safeguards approaches, DIV is a fundamental component. Variations in the approaches are mainly in the degree of C/S measures and in the types and numbers of material accountancy verification measures. The candidate safeguards approaches were evaluated toward the goal of determining a model safeguards approach. This model approach is based on the integrated application of selected safeguards measures to use International Atomic Energy Agency resources

  3. The integration of process monitoring for safeguards

    International Nuclear Information System (INIS)

    Cipiti, Benjamin B.; Zinaman, Owen R.

    2010-01-01

    The Separations and Safeguards Performance Model is a reprocessing plant model that has been developed for safeguards analyses of future plant designs. The model has been modified to integrate bulk process monitoring data with traditional plutonium inventory balances to evaluate potential advanced safeguards systems. Taking advantage of the wealth of operator data such as flow rates and mass balances of bulk material, the timeliness of detection of material loss was shown to improve considerably. Four diversion cases were tested including both abrupt and protracted diversions at early and late times in the run. The first three cases indicated alarms before half of a significant quantity of material was removed. The buildup of error over time prevented detection in the case of a protracted diversion late in the run. Some issues related to the alarm conditions and bias correction will need to be addressed in future work. This work both demonstrates the use of the model for performing diversion scenario analyses and for testing advanced safeguards system designs.

  4. Facility Safeguardability Analysis in Support of Safeguards by Design

    International Nuclear Information System (INIS)

    Wonder, E.F.

    2010-01-01

    The idea of 'Safeguards-by-Design' (SBD) means designing and incorporating safeguards features into new civil nuclear facilities at the earliest stages in the design process to ensure that the constructed facility is 'safeguardable,' i.e. will meet national and international nuclear safeguards requirements. Earlier consideration of safeguards features has the potential to reduce the need for costly retrofits of the facility and can result in a more efficient and effective safeguards design. A 'Facility Safeguardability Analysis' (FSA) would be a key step in Safeguards-by-Design that would link the safeguards requirements with the 'best practices', 'lessons learned', and design of the safeguards measures for implementing those requirements. The facility designer's nuclear safeguards experts would work closely with other elements of the project design team in performing FSA. The resultant analysis would support discussions and interactions with the national nuclear regulator (i.e. State System of Accounting for and Control of Nuclear Material - SSAC) and the IAEA for development and approval of the proposed safeguards system. FSA would also support the implementation of international safeguards by the IAEA, by providing them with a means to analyse and evaluate the safeguardability of facilities being designed and constructed - i.e. by independently reviewing and validating the FSA as performed by the design team. Development of an FSA methodology is part of a broader U.S. National Nuclear Security Administration program to develop international safeguards-by-design tools and guidance documents for use by facility designers. The NNSA NGSI -sponsored project team is looking, as one element of its work, at how elements of the methodology developed by the Generation IV International Forum's Working Group on Proliferation Resistance and Physical Protection can be adapted to supporting FSA. (author)

  5. Safeguards resource management

    International Nuclear Information System (INIS)

    Strait, R.S.

    1986-01-01

    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

  6. Strengthening Performance Management in the IAEA Department of Safeguards

    International Nuclear Information System (INIS)

    Villiers, V. Z. de

    2015-01-01

    This paper will describe an initiative to develop a management support tool to improve performance management in the IAEA Department of Safeguards. The envisaged mechanism should enable the Department to (a) plan, assess and report on the achievement of its objectives and (b) to improve its performance on a continuous basis. The performance management tool should be aligned with related processes in the Department and the IAEA as a whole such as strategic planning, programming and budget, the result-based management approach and various reporting mechanisms. It should be integrated with existing and planned information and other management systems. The initially, departmental working group that was established for this initiative focussed on two aspects: confirmation of the overall and specific objectives to be achieved by the Department of Safeguards, and compiling an inventory of indicators of activities, outputs and outcomes that were being used in the Department. This exercise confirmed that alignment and prioritization of activities relating to assessment of, and reporting on, performance could be improved. A value creation map was subsequently developed to assist in focussing the performance management tool to identified needs of stakeholders. Other activities of the working group included the determination of the desired characteristics of a hierarchy of performance indicators to be used to drive desired behaviour across organizational levels. Complexities to be handled included the following: · reflecting the appropriate component of the results chain (such as activities, outputs, outcomes and impact); · maintaining the linkages between objectives and performance indicators across organizational levels; · developing a balanced set of performance indicators (e.g. reflecting in-field and Headquarters activities, incorporating all main components of Departmental processes and balanced scorecard perspectives, measurable vs qualitative indicators); and

  7. EURATOM safeguards. Safeguards verifications in reprocessing plants

    International Nuclear Information System (INIS)

    Heppleston, M.

    1999-01-01

    This paper provides a brief historical view of the legal basis for EURATOM. The specific application of safeguards to large scale reprocessing plants, from the theoretical model to the practical application of inspection is considered. The challenge to adequately safeguard major commercial reprocessing facilities has led to many novel approaches being developed. These lessons will also benefit other safeguard projects as a result. Good cooperation between the operator and regulator is essential for the satisfactory installation of adequate safeguard controls. The use of modern data processing technology combined with other diverse monitoring techniques has shown that a major industrial scale reprocessing plant can be controlled under international safeguards to provide a high level of assurance [ru

  8. Performance monitoring of safeguards equipment

    International Nuclear Information System (INIS)

    Sirisena, K.; Peltoranta, M.; Goussarov, V.; Vodrazka, P.

    1999-01-01

    SGTCS is responsible for monitoring and reporting the performance of the SG equipment. Performance monitoring (PM) has been implemented in most important safeguards equipment operating unattended in nuclear facilities. Inspectors acquire equipment performance data in facilities. After inspection, the data package is submitted to SGTCS for processing and analysis. The performance data is used for identification of systems or components, which should be changed in the field and for identification of modules which, should be diagnosed at HQ in order to determine the cause of failure. Moreover, the performance data is used for preventive maintenance and spares distribution planning, and to provide statistics for official reports and management decision making. An important part of the performance monitoring is reporting. Equipment performance reports contain information about equipment inventory, utilization, failure types, failure distribution, and reliability. Trends in performance are given in graphical form in cases, where past data is available. Reliability estimates such as expected times between failures are provided. The automated reporting tools are obtainable through EMIS database application. (author)

  9. Beyond integrated safeguards: Performance-based assessments for future nuclear controls

    International Nuclear Information System (INIS)

    Pilat, Joseph F.; Budlong Sylvester, Kory W.

    2001-01-01

    Full text: In the future, if the nuclear nonproliferation and arms control agendas are to advance, they will likely become increasingly seen as parallel undertakings with the objective of comprehensive cradle-to-grave controls over nuclear materials and possibly even warheads removed from defense programs along with materials in civilian use. This 'back to the future' prospect was envisioned in the Acheson-Lillienthal Report and the Baruch Plan, and more modestly in the Atoms-for-Peace Proposal. Unlike the grand plans of the early nuclear years, today's and tomorrow's undertakings will more likely consist of a series of incremental steps with the goal of expanding nuclear controls. These steps will be undertaken at a time of fundamental change in the IAEA safeguards system, and they will be influenced by those changes in profound ways. This prospective influence needs to be taken into account as the IAEA develops and implements integrated safeguards, including its efforts to establish new safeguards criteria, undertake technological and administrative improvements in safeguards, implement credible capabilities for the detection of undeclared nuclear facilities and activities and, perhaps, provide for a more intensive involvement in applying safeguards in new roles such as the verification of a Fissile Material Cutoff Treaty. Performance-based criteria offer one promising way to address the effectiveness of integrated safeguards and to provide a common means of assessing the other key areas of a comprehensive approach to nuclear controls as these develop independently and to the extent that they are coordinated in the future. (author)

  10. Network modeling and analysis technique for the evaluation of nuclear safeguards systems effectiveness

    International Nuclear Information System (INIS)

    Grant, F.H. III; Miner, R.J.; Engi, D.

    1978-01-01

    Nuclear safeguards systems are concerned with the physical protection and control of nuclear materials. The Safeguards Network Analysis Procedure (SNAP) provides a convenient and standard analysis methodology for the evaluation of safeguards system effectiveness. This is achieved through a standard set of symbols which characterize the various elements of safeguards systems and an analysis program to execute simulation models built using the SNAP symbology. The reports provided by the SNAP simulation program enable analysts to evaluate existing sites as well as alternative design possibilities. This paper describes the SNAP modeling technique and provides an example illustrating its use

  11. Network modeling and analysis technique for the evaluation of nuclear safeguards systems effectiveness

    International Nuclear Information System (INIS)

    Grant, F.H. III; Miner, R.J.; Engi, D.

    1979-02-01

    Nuclear safeguards systems are concerned with the physical protection and control of nuclear materials. The Safeguards Network Analysis Procedure (SNAP) provides a convenient and standard analysis methodology for the evaluation of safeguards system effectiveness. This is achieved through a standard set of symbols which characterize the various elements of safeguards systems and an analysis program to execute simulation models built using the SNAP symbology. The reports provided by the SNAP simulation program enable analysts to evaluate existing sites as well as alternative design possibilities. This paper describes the SNAP modeling technique and provides an example illustrating its use

  12. Validating safeguards effectiveness given inherently limited test data

    International Nuclear Information System (INIS)

    Sicherman, A.

    1987-01-01

    A key issue in designing and evaluating nuclear safeguards systems is how to validate safeguards effectiveness against a spectrum of potential threats. Safeguards effectiveness is measured by a performance indicator such as the probability of defeating an adversary attempting a malevolent act. Effectiveness validation means a testing program that provides sufficient evidence that the performance indicator is at an acceptable level. Traditional statistical program when numerous independent system trials are possible. However, within the safeguards environment, many situations arise for which traditional statistical approaches may be neither feasible nor appropriate. Such situations can occur, for example, when there are obvious constraints on the number of possible tests due to operational impacts and testing costs. Furthermore, these tests are usually simulations (e.g., staged force-on-force exercises) rather than actual tests, and the system is often modified after each test. Under such circumstances, it is difficult to make and justify inferences about system performance by using traditional statistical techniques. In this paper, the authors discuss several alternative quantitative techniques for validating system effectiveness. The techniques include: (1) minimizing the number of required tests using sequential testing; (2) combining data from models inspections and exercises using Bayesian statistics to improve inferences about system performance; and (3) using reliability growth and scenario modeling to help specify which safeguards elements and scenarios to test

  13. Preliminary Performance Analysis Program Development for Safety System with Safeguard Vessel

    International Nuclear Information System (INIS)

    Kang, Han-Ok; Lee, Jun; Park, Cheon-Tae; Yoon, Ju-Hyeon; Park, Keun-Bae

    2007-01-01

    SMART is an advanced modular integral type pressurized water reactor for a seawater desalination and an electricity production. Major components of the reactor coolant system such as the pressurizer, Reactor Coolant Pump (RCP), and steam generators are located inside the reactor vessel. The SMART can fundamentally eliminate the possibility of large break loss of coolant accidents (LBLOCAs), improve the natural circulation capability, and better accommodate and thus enhance a resistance to a wide range of transients and accidents. The safety goals of the SMART are enhanced through highly reliable safety systems such as the passive residual heat removal system (PRHRS) and the safeguard vessel coupled with the passive safety injection feature. The safeguard vessel is a steel-made, leak-tight pressure vessel housing the RPV, SIT, and the associated valves and pipelines. A primary function of the safeguard vessel is to confine any radioactive release from the primary circuit within the vessel under DBAs related to loss of the integrity of the primary system. A preliminary performance analysis program for a safety system using the safeguard vessel is developed in this study. The developed program is composed of several subroutines for the reactor coolant system, passive safety injection system, safeguard vessel including the pressure suppression pool, and PRHRS. A small break loss of coolant accident at the upper part of a reactor is analyzed and the results are discussed

  14. IAEA Safeguards: Status and prospects

    International Nuclear Information System (INIS)

    Gruemm, H.

    1983-01-01

    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)

  15. A database model for evaluating material accountability safeguards effectiveness against protracted theft

    International Nuclear Information System (INIS)

    Sicherman, A.; Fortney, D.S.; Patenaude, C.J.

    1993-07-01

    DOE Material Control and Accountability Order 5633.3A requires that facilities handling special nuclear material evaluate their effectiveness against protracted theft (repeated thefts of small quantities of material, typically occurring over an extended time frame, to accumulate a goal quantity). Because a protracted theft attempt can extend over time, material accountability-like (MA) safeguards may help detect a protracted theft attempt in progress. Inventory anomalies, and material not in its authorized location when requested for processing are examples of MA detection mechanisms. Crediting such detection in evaluations, however, requires taking into account potential insider subversion of MA safeguards. In this paper, the authors describe a database model for evaluating MA safeguards effectiveness against protracted theft that addresses potential subversion. The model includes a detailed yet practical structure for characterizing various types of MA activities, lists of potential insider MA defeat methods and access/authority related to MA activities, and an initial implementation of built-in MA detection probabilities. This database model, implemented in the new Protracted Insider module of ASSESS (Analytic System and Software for Evaluating Safeguards and Security), helps facilitate the systematic collection of relevant information about MA activity steps, and ''standardize'' MA safeguards evaluations

  16. Evolution of safeguards systems design

    International Nuclear Information System (INIS)

    Shipley, J.P.; Christensen, E.L.; Dietz, R.J.

    1979-01-01

    Safeguards systems play a vital detection and deterrence role in current nonproliferation policy. These safeguards systems have developed over the past three decades through the evolution of three essential components: the safeguards/process interface, safeguards performance criteria, and the technology necessary to support effective safeguards. This paper discusses the background and history of this evolutionary process, its major developments and status, and the future direction of safeguards system design

  17. The Use of Performance Metrics for the Assessment of Safeguards Effectiveness at the State Level

    Energy Technology Data Exchange (ETDEWEB)

    Bachner K. M.; George Anzelon, Lawrence Livermore National Laboratory, Livermore, CA Yana Feldman, Lawrence Livermore National Laboratory, Livermore, CA Mark Goodman,Department of State, Washington, DC Dunbar Lockwood, National Nuclear Security Administration, Washington, DC Jonathan B. Sanborn, JBS Consulting, LLC, Arlington, VA.

    2016-07-24

    In the ongoing evolution of International Atomic Energy Agency (IAEA) safeguards at the state level, many safeguards implementation principles have been emphasized: effectiveness, efficiency, non-discrimination, transparency, focus on sensitive materials, centrality of material accountancy for detecting diversion, independence, objectivity, and grounding in technical considerations, among others. These principles are subject to differing interpretations and prioritizations and sometimes conflict. This paper is an attempt to develop metrics and address some of the potential tradeoffs inherent in choices about how various safeguards policy principles are implemented. The paper carefully defines effective safeguards, including in the context of safeguards approaches that take account of the range of state-specific factors described by the IAEA Secretariat and taken note of by the Board in September 2014, and (2) makes use of performance metrics to help document, and to make transparent, how safeguards implementation would meet such effectiveness requirements.

  18. A model to improve efficiency and effectiveness of safeguards measures

    International Nuclear Information System (INIS)

    D'Amato, Eduardo; Llacer, Carlos; Vicens, Hugo

    2001-01-01

    Full text: The main purpose of our current studies is to analyse the measures to be adopted tending to integrate the traditional safeguard measures to the ones stated in the Additional Protocol (AP). A simplified nuclear fuel cycle model is considered to draw some conclusions on the application of integrated safeguard measures. This paper includes a briefing, describing the historical review that gave birth to the A.P. and proposes a model to help the control bodies in the making decision process. In May 1997, the Board of Governors approved the Model Additional Protocol (MAP) which aimed at strengthening the effectiveness and improving the efficiency of safeguard measures. For States under a comprehensive safeguard agreement the measures adopted provide credible assurance on the absence of undeclared nuclear material and activities. In September 1999, the governments of Argentina and Brazil formally announced in the Board of Governors that both countries would start preliminary consultations on one adapted MAP applied to the Agreement between the Republic of Argentina, the Federative Republic of Brazil, the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials and the International Atomic Energy Agency for the Application of Safeguards (Quatripartite Agreement/INFCIRC 435). In December 1999, a first draft of the above mentioned document was provided as a starting point of discussion. During the year 2000 some modifications to the original draft took place. These were the initial steps in the process aiming at reaching the adequate conditions to adhere to the A.P. in each country in a future Having in mind the future AP implementation, the safeguards officers of the Regulatory Body of Argentina (ARN) began to think about the future simultaneous application of the two types of safeguards measures, the traditional and the non traditional ones, what should converge in an integrated system. By traditional safeguards it is understood quantitative

  19. Building safeguards infrastructure

    International Nuclear Information System (INIS)

    Stevens, Rebecca S.; McClelland-Kerr, John

    2009-01-01

    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 these three areas - sometimes referred to as 3S, for safety, security and safeguards - is essential to supporting the growth of nuclear power, and the infrastructure that supports them should be strengthened. The focus of this paper will be on the role safeguards plays in the 3S concept and how to support the development of the infrastructure necessary to support safeguards. The objective of this paper has been to provide a working definition of safeguards infrastructure, and to discuss xamples of how building safeguards infrastructure is presented in several models. The guidelines outlined in the milestones document provide a clear path for establishing both the safeguards and the related infrastructures needed to support the development of nuclear power. The model employed by the INSEP program of engaging with partner states on safeguards-related topics that are of current interest to the level of nuclear development in that state provides another way of approaching the concept of building safeguards infrastructure. The Next Generation Safeguards Initiative is yet another approach that underscored five principal areas for growth, and the United States commitment to working with partners to promote this growth both at home and abroad.

  20. A Safeguardability Check-List for Safeguards by Design

    Energy Technology Data Exchange (ETDEWEB)

    Sevini, F. [European Commission - Joint Research Centre, Institute for Transuranium Elements, Nuclear Security Unit, Ispra (Italy); Renda, G. [European Commission, DG Energy, Directorate E ' Nuclear Safeguards' , Unit 4 ' Inspections: reactors, storages and others facilities, Luxembourg (Luxembourg); Sidlova, V. [European Commission - Joint Research Centre, Institute for Transuranium Elements, Nuclear Security Unit, Ispra (Italy)

    2011-12-15

    Safeguards by design is a complex step-by-step interactive decision process involving various stake-holders and design choices to be made over a certain period of time. The resulting plant design should be a compromise among economical, safety, security and safeguards implementation constraints. Access to technology and equipment, as well as to the nuclear fuel cycle, determines the basic choices that the designer has to make. Once the boundary conditions for a given facility have been fixed, the designer still faces the challenge of setting several design and operational parameters that will require various trade-offs . Concerning safeguards, these can be seen in three groups, i.e. those related to the general design and its intrinsic proliferation resistance; those related to the specific lay-out and planning; those related to the actual safeguards instrumentation, its effectiveness and efficiency. The paper aims at describing a model for a phased, or 'layered' approach to safeguards-by-design, focusing on the example of off-load reactors.

  1. Promoting Safeguards Best Practice through the Asia-Pacific Safeguards Network (APSN)

    International Nuclear Information System (INIS)

    Floyd, R.; Everton, C.; Lestari, S.

    2015-01-01

    There is a growing international focus on effective regulatory oversight of nuclear energy across the three pillars of nuclear safety, security and safeguards. Regarding nuclear safeguards, States in the Asia-Pacific region recognize the importance of cooperation and sharing of experiences to ensure that this is implemented to high international standards. For this reason the Asia-Pacific Safeguards Network (APSN) was formed in 2009 - an informal network of departments, agencies and regulatory authorities with safeguards responsibilities from some 15 countries across the Asia-Pacific region. The objective of APSN it to bring States in the region together to develop practical measures for enhancing effective safeguards implementation, through workshops, sharing experiences and other safeguards projects. APSN works closely with the IAEA to achieve these objectives. This paper will outline the role and objectives of APSN and provide examples of how APSN work together to enhance safeguards effectiveness and raise awareness. The paper will also explore how this model of a broad community of States working together on safeguards could enhance implementation and awareness in other regions of the world. (author)

  2. Safeguards document (INFCIRC/153) and the new safeguards system

    International Nuclear Information System (INIS)

    Haginoya, Tohru

    1997-01-01

    INFCIRC/153. The NPT covers nuclear weapons and nuclear explosive devices but not other military uses of nuclear materials. The NPT safeguards applies all nuclear materials including undeclared nuclear materials. The protection of commercially sensitive information is important. The new safeguards system. The Model protocol amends INFCIRC/153 (the Protocol prevails). Apply nuclear fuel cycle related activities with no nuclear material. The environmental monitoring is an important measure, but non-weapon countries have no such technology. Impact and benefit from the new system. Simplification of the conventional safeguards. Could possibly define three categories of plutonium. (author)

  3. The safeguards active response inventory system (SARIS)

    International Nuclear Information System (INIS)

    Carlson, R.L.; Hairston, L.A.; O'Callaghan, P.B.; Grambihler, A.J.; Ruemmler, W.P.

    1987-01-01

    The Safeguards Active Response Inventory System (SARIS) is a computerized accountability system developed for nuclear materials control that incorporates elements of process monitoring, criticality safety, physical inventory and safeguards. It takes data from the process operations, stores it in an on-line database and translates the information into the formats needed by the various users. It traces the material through the process from feed to product; including recycle, waste and scraps streams. It models the process as the material changes form to ensure that artificial losses are not created. It automatically generates input to Nuclear Materials Management and Safeguards System (NMMSS), performs checks to prevent the possibility of a criticality accident, prepares an audit trail for Safeguards, prints labels for nuclear material containers, and produces DOE/NRC 741 forms. SARIS has been installed at three laboratories across the country

  4. Safeguards resource management

    International Nuclear Information System (INIS)

    Strait, R.S.

    1986-01-01

    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 systems 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 cost 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

  5. Risk analysis of nuclear safeguards regulations

    International Nuclear Information System (INIS)

    Al-Ayat, R.A.; Altman, W.D.; Judd, B.R.

    1982-06-01

    The Aggregated Systems Model (ASM), a probabilisitic risk analysis tool for nuclear safeguards, was applied to determine benefits and costs of proposed amendments to NRC regulations governing nuclear material control and accounting systems. The objective of the amendments was to improve the ability to detect insiders attempting to steal large quantities of special nuclear material (SNM). Insider threats range from likely events with minor consequences to unlikely events with catastrophic consequences. Moreover, establishing safeguards regulations is complicated by uncertainties in threats, safeguards performance, and consequences, and by the subjective judgments and difficult trade-offs between risks and safeguards costs. The ASM systematically incorporates these factors in a comprehensive, analytical framework. The ASM was used to evaluate the effectiveness of current safeguards and to quantify the risk of SNM theft. Various modifications designed to meet the objectives of the proposed amendments to reduce that risk were analyzed. Safeguards effectiveness was judged in terms of the probability of detecting and preventing theft, the expected time to detection, and the expected quantity of SNM diverted in a year. Data were gathered in tours and interviews at NRC-licensed facilities. The assessment at each facility was begun by carefully selecting scenarios representing the range of potential insider threats. A team of analysts and facility managers assigned probabilities for detection and prevention events in each scenario. Using the ASM we computed the measures of system effectiveness and identified cost-effective safeguards modifications that met the objectives of the proposed amendments

  6. Reactor safeguards system assessment and design. Volume I

    International Nuclear Information System (INIS)

    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

  7. Safeguards systems parameters

    International Nuclear Information System (INIS)

    Avenhaus, R.; Heil, J.

    1979-01-01

    In this paper analyses are made of the values of those parameters that characterize the present safeguards system that is applied to a national fuel cycle; those values have to be fixed quantitatively so that all actions of the safeguards authority are specified precisely. The analysis starts by introducing three categories of quantities: The design parameters (number of MBAs, inventory frequency, variance of MUF, verification effort and false-alarm probability) describe those quantities whose values have to be specified before the safeguards system can be implemented. The performance criteria (probability of detection, expected detection time, goal quantity) measure the effectiveness of a safeguards system; and the standards (threshold amount and critical time) characterize the magnitude of the proliferation problem. The means by which the values of the individual design parameters can be determined with the help of the performance criteria; which qualitative arguments can narrow down the arbitrariness of the choice of values of the remaining parameters; and which parameter values have to be fixed more or less arbitrarily, are investigated. As a result of these considerations, which include the optimal allocation of a given inspection effort, the problem of analysing the structure of the safeguards system is reduced to an evaluation of the interplay of only a few parameters, essentially the quality of the measurement system (variance of MUF), verification effort, false-alarm probability, goal quantity and probability of detection

  8. 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)

  9. Accountability and non-proliferation nuclear regime: a review of the mutual surveillance Brazilian-Argentine model for nuclear safeguards

    International Nuclear Information System (INIS)

    Xavier, Roberto Salles

    2014-01-01

    The regimes of accountability, the organizations of global governance and institutional arrangements of global governance of nuclear non-proliferation and of Mutual Vigilance Brazilian-Argentine of Nuclear Safeguards are the subject of research. The starting point is the importance of the institutional model of global governance for the effective control of non-proliferation of nuclear weapons. In this context, the research investigates how to structure the current arrangements of the international nuclear non-proliferation and what is the performance of model Mutual Vigilance Brazilian-Argentine of Nuclear Safeguards in relation to accountability regimes of global governance. For that, was searched the current literature of three theoretical dimensions: accountability, global governance and global governance organizations. In relation to the research method was used the case study and the treatment technique of data the analysis of content. The results allowed: to establish an evaluation model based on accountability mechanisms; to assess how behaves the model Mutual Vigilance Brazilian-Argentine Nuclear Safeguards front of the proposed accountability regime; and to measure the degree to which regional arrangements that work with systems of global governance can strengthen these international systems. (author)

  10. Aggregated systems model for nuclear safeguards decisions

    International Nuclear Information System (INIS)

    1979-03-01

    This report summarizes a general analytical tool designed to assist nuclear safeguards decision-makers. The approach is based on decision analysis--a quantitative procedure for evaluating complex decision alternatives with uncertain outcomes. The report describes the general analytical approach in the context of safeguards decisions at a hypothetical nuclear fuel reprocessing plant

  11. Safeguards Network Analysis Procedure (SNAP): overview

    International Nuclear Information System (INIS)

    Chapman, L.D; Engi, D.

    1979-08-01

    Nuclear safeguards systems provide physical protection and control of nuclear materials. The Safeguards Network Analysis Procedure (SNAP) provides a convenient and standard analysis methodology for the evaluation of physical protection system effectiveness. This is achieved through a standard set of symbols which characterize the various elements of safeguards systems and an analysis program to execute simulation models built using the SNAP symbology. The outputs provided by the SNAP simulation program supplements the safeguards analyst's evaluative capabilities and supports the evaluation of existing sites as well as alternative design possibilities. This paper describes the SNAP modeling technique and provides an example illustrating its use

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

    International Nuclear Information System (INIS)

    2015-01-01

    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

  13. Combined SAFE/SNAP approach to safeguards evaluation

    International Nuclear Information System (INIS)

    Engi, D.; Chapman, L.D.; Grant, F.H.; Polito, J.

    1980-01-01

    Generally, the scope of a safeguards evaluation model can efficiently address one of two issues, (1) global safeguards effectiveness, or (2) vulnerability analysis for individual scenarios. The Safeguards Automated Facility Evaluation (SAFE) focuses on (1) while the Safeguards Network Analysis Procedure (SNAP) is directed at (2). SAFE addresses (1) in that it considers the entire facility, i.e., the composite system of hardware and human components, in one global analysis. SNAP addresses (2) by providing a safeguards modeling symbology sufficiently flexible to represent quite complex scenarios from the standpoint of hardware interfaces while also accounting for a rich variety of human decision making. A combined SAFE/SNAP approach to the problem of safeguards evaluation is described and illustrated through an example

  14. Combined SAFE/SNAP approach to safeguards evaluation

    International Nuclear Information System (INIS)

    Engi, D.; Chapman, L.D.; Grant, F.H.; Polito, J.

    1980-01-01

    The scope of a safeguards evaluation model can efficiently address one of two issues: (1) global safeguards effectiveness or (2) vulnerability analysis for individual scenarios. The Safeguards Automated Facility Evaluation (SAFE) focuses on the first issue, while the Safeguards Network Analysis Procedure (SNAP) is directed towards the second. A combined SAFE/SNAP approach to the problem of safeguards evaluation is described and illustrated through an example. 4 refs

  15. How safe are nuclear safeguards

    International Nuclear Information System (INIS)

    Sullivan, E.

    1979-01-01

    Reports of weaknesses in IAEA safeguards have alarmed the US and since September 1977, US officials have refused to certify that the IAEA can adequately safeguard nuclear material the US exports. For political reasons, the IAEA safeguards system cannot perform an actual policing role or physically protect strategic material. The IAEA can only send out inspectors to verify bookkeeping and install cameras to sound the alarm should a diversion occur. Based on these IAEA reports and on interviews with scientists and US officials, the following serious problems hampering the Agency's safeguards effort can be identified: no foolproof safeguards for commercial reprocessing plants, uranium enrichment facilities, or fast breeder reactors; equipment failure and unreliable instruments; faulty accounting methods; too few well-trained inspectors; restrictions on where inspectors can go; commercial conflicts. Programs by the US, Canada, West Germany, Japan, and developing nations devised to better safeguards are briefly discussed. Some experts question whether international safeguards can be improved quickly enough to successfully deter nuclear weapons proliferation, given the rapid spread of nuclear technology to the third world

  16. VISA-2 - a general, vulnerability-oriented method for evaluating the performance of integrated safeguards/security systems at nuclear facilities

    International Nuclear Information System (INIS)

    Harris, L.; Owel, W.R.

    1981-01-01

    This paper discusses the VISA (Vulnerability of Integrated Safeguards Analysis) method, developed in 1976-77 for the Nuclear Regulatory Commission, and which has been adapted more recently to a broader range of uses. The performance of VISA systems is evaluated in terms of how they perform as an integrated safeguards/security system. The resulting method has been designated VISA-2. 7 refs

  17. Safeguards as an evolutionary system

    International Nuclear Information System (INIS)

    Carlson, J.

    1998-01-01

    NPT safeguards pursuant to INFCIRC/153 retain a strong emphasis on materials accountancy, and are primarily concerned with verifying nuclear activities as declared by the State - the correctness of States' declarations. This decade, failure to adequately address the possibility of undeclared nuclear activities - the issue of the completeness of States' declarations - has been recognized as a major shortcoming in the safeguards system. Since the 'classical' safeguards system is unable to provide credible assurance of the absence of clandestine nuclear activities, substantial efforts are being made to strengthen the IAEA's capabilities in this regard. Agreement has been reached on a Model Protocol substantially extending the Agency's authority, and good progress has been made in developing the new approaches, technologies and techniques required to ensure this authority is used effectively. Increasingly, safeguards will involve more qualitative judgements. Transparency will be very important - without a clear understanding by Member States of how the Agency goes about its new tasks and reaches its conclusions about the absence of undeclared activities, the safeguards system will not fulfil its vital confidence-building role. A major theme in current safeguards thinking is integration, the rationalization of classical safeguards with the new safeguards strengthening measures. As part of the rationalization process, it is timely to re-assess traditional safeguards implementation practices. One of these is uniformity in the way safeguards activities are implemented in different States. Another is whether the traditional concept of safeguards confidentiality is consistent with the increasing importance of transparency. (author)

  18. The international safeguards and domestic safeguards and security interface

    International Nuclear Information System (INIS)

    Whitworth, A.

    1996-01-01

    The International Safeguards Division, in conjunction with the Office of Safeguards and Security, organized a workshop on the international safeguards/domestic safeguards and security interface that was held in March 1996. The purpose of the workshop was to identify and resolve domestic safeguards and security issues associated with the implementation of International Atomic Energy Agency (IAEA) safeguards in the Department of Energy (DOE) complex. The workshop drew heavily upon lessons learned in the application of IAEA safeguards at storage facilities in oak Ridge, Hanford, and Rocky Flats. It was anticipated that the workshop would facilitate a consistent DOE safeguards and security approach for the implementation of IAEA safeguards in the DOE complex. This paper discusses the issues and resolutions of several issues raised at the workshop that involve primarily the domestic material control and accountability program

  19. Future directions for international safeguards - ESARDA WG on integrated safeguards

    International Nuclear Information System (INIS)

    Rezniczek, A.

    2013-01-01

    Reducing IAEA inspection effort does not mean that the overall safeguards effort will be reduced. There will be compensation and additional effort spent by states and SSACs (State Systems of Accounting and Control). State and/or regional authorities take very serious their responsibilities to safeguard the nuclear material. Enhanced cooperation between all players should be more seriously considered by the IAEA. A more effective implementation of the principle 'one job - one person' and sub-delegation of verification tasks should be taken into account for future evolution. At present, the state level approach is still based on a bottom up approach and not developed top down. The basis is still an aggregation of the facility specific safeguards approaches with some minor adjustments by state specific factors. The touchstone for a true state level approach would be a top-down development process with the result that safeguards effort spent in a state is no longer strongly correlated to the amount and quality of nuclear material in that state. The limitation of the Physical Model is that only the technical aspects are reflected. To actually perform a proliferation, the technical capability is a necessary but insufficient condition. Besides the pure technical capabilities, one has to consider the feasibility for a state to actually implement a proliferation action in its given environment. Factors to be considered are for example institutional factors, ownership of facilities and social and political structures in the state. The help a purely technical assessment can provide is also limited in cases where states have a well developed fuel cycle and thus have at their disposal all required technical capabilities. The paper is followed by the slides of the presentation. (authors)

  20. Some developments in safeguards techniques

    International Nuclear Information System (INIS)

    Beets, C.

    1977-01-01

    The fundamental principles of safeguards and the research and development of safeguards techniques are described. Safeguard accountancy based upon the partition of the fuel cycle into suitable material balance areas will be further improved. Implementation of international safeguards in the European fuel fabrication and reprocessing facilities is described. The effectiveness of a material accounting system depends on the quality of the quantitative data. The allocation of the tasks in the framework of an integrated safeguards is concerned with R and D work only and has no bearing on the allocation of the implementation costs. Bulk measurements, sampling and destructive or non-destructive analysis of samples are described for the determination of batch data. Testing of the safeguards techniques as a keystone in relation to plant instrumentation programmes are still being developed throughout the world. In addition to accountancy and control, it also includes an effective physical security program. The system of international safeguards that prevailed in the sixties has been re-modelled to comply with the new requirements of the Non-Proliferation Treaty and with the growth of nuclear energy

  1. 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

  2. Safeguards effectiveness criteria and safeguards efficiency

    International Nuclear Information System (INIS)

    Stein, G.; Canty, M.J.; Knapp, U.; Munch, E.

    1983-01-01

    A critical examination of current tendencies in quantification, assessment and enhancement of the effectiveness of international safeguards is undertaken. It is suggested that the present narrow and overly technical interpretation of some elements of international safeguards is both impractical and detrimental. A pragmatic, case-bycase approach is called for to implement the provisions of safeguards agreements in a more balanced, efficient way

  3. Safeguards management inspection procedures

    International Nuclear Information System (INIS)

    Barth, M.J.; Dunn, D.R.

    1984-08-01

    The objective of this inspection module is to independently assess the contributions of licensee management to overall safeguards systems performance. The inspector accomplishes this objective by comparing the licensee's safeguards management to both the 10 CFR, parts 70 and 73, requirements and to generally accepted management practices. The vehicle by which this comparison is to be made consists of assessment questions and key issues which point the inspector to areas of primary concern to the NRC and which raise additional issues for the purpose of exposing management ineffectiveness. Further insight into management effectiveness is obtained through those assessment questions specifically directed toward the licensee's safeguards system performance. If the quality of the safeguards is poor, then the inspector should strongly suspect that management's role is ineffective and should attempt to determine management's influence (or lack thereof) on the underlying safeguards deficiencies. (The converse is not necessarily true, however.) The assessment questions in essence provide an opportunity for the inspector to identify, to single out, and to probe further, questionable management practices. Specific issues, circumstances, and concerns which point to questionable or inappropriate practices should be explicitly identified and referenced against the CFR and the assessment questions. The inspection report should also explain why the inspector feels certain management practices are poor, counter to the CFR, and/or point to ineffecive management. Concurrent with documenting the inspection results, the inspector should provide recommendations for alleviating observed management practices that are detrimental to effective safeguards. The recommendations could include: specific changes in the practices of the licensee, followup procedures on the part of NRC, and proposed license changes

  4. The international safeguards profession

    International Nuclear Information System (INIS)

    Sanders, K.E.

    1986-01-01

    The International Atomic Energy Agency has established a staff of safeguards professionals who are responsible for carrying out on-site inspections to determine compliance with international safeguards agreements. By IAEA Statute, the paramount consideration in recruiting IAEA staff is to secure employees of the highest standards of efficiency, technical competence, and integrity. An analysis of the distribution of professionals in the IAEA Department of Safeguards has revealed some interesting observations regarding the distribution of grade levels, age, time in service, gender, and geographical origin. Following several earlier studies performed by contractors for ACDA, U.S. efforts have been undertaken to attract and better prepare candidates for working at the IAEA

  5. Recent advances in IAEA safeguards systems analysis

    International Nuclear Information System (INIS)

    Bahm, W.; Ermakov, S.; Kaniewski, J.; Lovett, J.; Pushkarjov, V.; Rosenthal, M.D.

    1983-01-01

    Efficient implementation of effective safeguards, the objective of the IAEA's Department of Safeguards, would be unthinkable without carrying out systematic studies on many different problems related to technical and other aspects of safeguards. The System Studies Section of the Department concentrates its efforts on such studies with the purpose of elaborating concepts, criteria, approaches and rules for the implementation of safeguards. In particular, the Section elaborates concepts and approaches for applying safeguards at the complex facilities that are expected to enter under safeguards in the future, develops approaches and rules in the areas where the Agency is still gaining experience, and assists in the implementation of safeguards whenever problems requiring non-routine solutions arise. This paper presents examples of the present activities of the System Studies Section: development of guidelines for use by facility designers in order to make safeguards easier and more effective, studies on near-real-time material accountancy, preparation of safeguards approaches for specific facility types, preparation of model inspection activity lists for different facility types and alternative safeguards approaches and preparation of safeguards policy papers containing the rules and regulations to be followed in the design and implementation of safeguards. (author)

  6. Evolution of the Nuclear Safeguards Performance Laboratory PERLA on the Ispra Site of the Institute for Transuranium Elements

    International Nuclear Information System (INIS)

    Berndt, R.; Abbas, K.; Berthou, V.; De Almeida Carrapico, C.; Forcina, V.; Mayorov, V.; Mortreau, P.; Mosconi, M.; Pedersen, B.; Peerani, P.; Rosas, F.; Tagziria, H.; Tomanin, A.; Rozite, A.; Marin-Ferrer, M.; Crochemore, J.-M.; Roesgen, E.; Janssens, W.A.M.; )

    2015-01-01

    Based upon the experience of many years of operation, the safeguards Performance Laboratory PERLA will be reshaped in the near future (and relocated on the Ispra site such as not to interfere with decommissioning activities). During almost 30 years of successfully operating nuclear facilities in Ispra for supporting nuclear safeguards inspectorates with R&D, equipment development and training for in the meantime more than 1250 trainees, this laboratory is the main work-horse in this field and has functioned very frequently in the last years as easily accessible nuclear laboratory for external users. Even if a constant evolution took place in the last years, and additional facilities like the active neutron laboratory PUNITA or the ITRAP test laboratory for nuclear security R&D, testing and training have been taken in service, this step-change will allow refiguring the laboratory to face also new user expectations. NDA for safeguards continues to be a cornerstone of the measurement capacities complemented by experimental and advanced approaches, such as using active neutron interrogation, automation of measurements, complemented by Monte-Carlo simulations for neutron and gamma radiation. The tendency is also to integrate multiple plant signals (not only NDA measurements) in an overall assessment scheme and we envisage offering training and exercising capabilities for the inspectors also in this direction in the future. This paper will thus provide some insight in the concepts for the future use of the nuclear facilities on the Ispra site, which is complementary to two other contributions to this symposium, i.e., one describing the activities of our sister unit in Karlsruhe on NDA Safeguards Training and another on the new Advanced Safeguards Measurement, Monitoring and Modelling Laboratory (AS3ML) being built currently in Ispra. (author)

  7. Some basic concepts of fast breeder reactor safeguards

    International Nuclear Information System (INIS)

    Tkharev, E.; Walford, F.J.

    1987-04-01

    The range of discussion topics of this report is restricted to a few key areas of safeguards importance at Fast Breeder Reactors (FBR) only. The differences between thermal and fast reactors that may have safeguards significance in the case of FBRs are listed. The FBR principles of design are mentioned. The relevant safeguards objectives and criteria are given. The fundamental issues for safeguarding FBR are treated. An outline safeguards approach is presented. Model inspection activities are mentioned. 4 figs

  8. Project Report on Development of a Safeguards Approach for Pyroprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Robert Bean

    2010-09-01

    The Idaho National Laboratory has undertaken an effort to develop a standard safeguards approach for international commercial pyroprocessing facilities. This report details progress for the fiscal year 2010 effort. A component by component diversion pathway analysis has been performed, and has led to insight on the mitigation needs and equipment development needed for a valid safeguards approach. The effort to develop an in-hot cell detection capability led to the digital cloud chamber, and more importantly, the significant potential scientific breakthrough of the inverse spectroscopy algorithm, including the ability to identify energy and spatial location of gamma ray emitting sources with a single, non-complex, stationary radiation detector system. Curium measurements were performed on historical and current samples at the FCF to attempt to determine the utility of using gross neutron counting for accountancy measurements. A solid cost estimate of equipment installation at FCF has been developed to guide proposals and cost allocations to use FCF as a test bed for safeguards measurement demonstrations. A combined MATLAB and MCNPX model has been developed to perform detector placement calculations around the electrorefiner. Early harvesting has occurred wherein the project team has been requested to provide pyroprocessing technology and safeguards short courses.

  9. Model of a Generic Natural Uranium Conversion Plant ? Suggested Measures to Strengthen International Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Raffo-Caiado, Ana Claudia [ORNL; Begovich, John M [ORNL; Ferrada, Juan J [ORNL

    2009-11-01

    This is the final report that closed a joint collaboration effort between DOE and the National Nuclear Energy Commission of Brazil (CNEN). In 2005, DOE and CNEN started a collaborative effort to evaluate measures that can strengthen the effectiveness of international safeguards at a natural uranium conversion plant (NUCP). The work was performed by DOE s Oak Ridge National Laboratory and CNEN. A generic model of a NUCP was developed and typical processing steps were defined. Advanced instrumentation and techniques for verification purposes were identified and investigated. The scope of the work was triggered by the International Atomic Energy Agency s 2003 revised policy concerning the starting point of safeguards at uranium conversion facilities. Prior to this policy only the final products of the uranium conversion plant were considered to be of composition and purity suitable for use in the nuclear fuel cycle and therefore, subject to the IAEA safeguards control. DOE and CNEN have explored options for implementing the IAEA policy, although Brazil understands that the new policy established by the IAEA is beyond the framework of the Quadripartite Agreement of which it is one of the parties, together with Argentina, the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC) and the IAEA. Two technical papers on this subject were published at the 2005 and 2008 INMM Annual Meetings.

  10. Structure for the decomposition of safeguards responsibilities

    International Nuclear Information System (INIS)

    Dugan, V.L.; Chapman, L.D.

    1977-01-01

    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. Structure for the decomposition of safeguards responsibilities

    International Nuclear Information System (INIS)

    Dugan, V.L.; Chapman, L.D.

    1977-08-01

    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

  12. IAEA safeguards glossary. 2001 ed

    International Nuclear Information System (INIS)

    2002-01-01

    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

  13. IAEA safeguards glossary. 2001 ed

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-06-01

    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

  14. IAEA safeguards glossary. 2001 ed

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-06-01

    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

  15. IAEA safeguards glossary. 2001 ed

    International Nuclear Information System (INIS)

    2002-01-01

    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

  16. Proliferation Resistance and Safeguards by Design: The Safeguardability Assessment Tool Provided by the INPRO Collaborative Project ''INPRO'' (Proliferation Resistance and Safeguardability Assessment)

    International Nuclear Information System (INIS)

    Haas, E.; Chang, H.-L.; Phillips, J.R.; Listner, C.

    2015-01-01

    analysis), and the identification of safeguards tools and measures to meet facility or activity specific safeguards objectives. The usefulness of this approach has been preliminary tested and demonstrated in a case study performed by KAERI. (author)

  17. Safeguards by design - The early consideration of safeguards concepts

    International Nuclear Information System (INIS)

    Killeen, T.; Moran, B.; Pujol, E.

    2009-01-01

    Full-text: The IAEA Department of Safeguards is in the process of formalizing its approach to long-range strategic planning. As a result of this activity new endeavours are being identified. One of these endeavours is to develop a concept known as Safeguards by Design. Safeguarding nuclear material and facilities can be made more effective and cost efficient by improving the safeguardability of the system. By taking into account design features that facilitate the implementation of international safeguards early in the design phase, a concept known as safeguards by design, the proliferation resistance of the system can be improved. This improvement process requires an understanding by designers and operators of safeguards and its underlying principles. To advance the safeguards by design approach, the IAEA determined that there is a need to develop written guidance. This guidance would help the major stakeholders - the designers, operators, owners, and regulatory bodies - to better understand how a facility could be designed, built and operated in such a way that effective safeguards could be implemented at reduced cost and with minimal burden to facility operations. By enlisting the cooperation of Member States through the support programme structure, the IAEA is working to first develop a document that describes the basic principles of safeguards, and the fundamental design features and measures that facilitate the implementation of international safeguards. Facility-specific guidance will then be developed utilizing the resources, expertise and experience of the IAEA and its Member States. This paper will review the foundation for the development of this task, describe the progress that has been made and outline the path forward. (author)

  18. 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.

  19. Status of Safeguards and Separations Model Development at Plant and Molecular Levels

    Energy Technology Data Exchange (ETDEWEB)

    de Almeida, Valmor F [ORNL; Hay, Benjamin [ORNL; DePaoli, David W [ORNL

    2009-10-01

    A primary goal of the Safeguards and Separations IPSC effort is the development of process modeling tools that allow dynamic simulations of separations plant operations under various configurations and conditions, and integration of relevant safeguards analyses. A requirement of the effort is to develop codes on modern, expandable architectures, with flexibility to explore and evaluate a wide range of process options. During FY09, efforts at ORNL have been focused on two priority tasks toward achieving the IPSC goal: (1) a top-down exploration of architecture - Subtask 1: Explore framework for code development and integration for plant-level simulation; and (2) a bottom-up fundamental modeling effort - Subtask 2: Development of molecular-level agent design code. Subtask 1 is important because definition and development of architecture is a key issue for the overall effort, as selection of an overall approach and code/data requirements is a necessary first step in the organization, design and development of separations and safeguards codes that will be incorporated. The agent design effort of Subtask 2 is a molecular-level modeling effort that has a direct impact on a near-term issue of the Separations and Waste Forms Campaign. A current focus of experimental efforts is the development of robust agents and processes for separation of Am/Cm. Development of enhanced agent-design codes will greatly accelerate discovery and experimental testing.

  20. Status of Safeguards and Separations Model Development at Plant and Molecular Levels

    International Nuclear Information System (INIS)

    de Almeida, Valmor F.; Hay, Benjamin; DePaoli, David W.

    2009-01-01

    A primary goal of the Safeguards and Separations IPSC effort is the development of process modeling tools that allow dynamic simulations of separations plant operations under various configurations and conditions, and integration of relevant safeguards analyses. A requirement of the effort is to develop codes on modern, expandable architectures, with flexibility to explore and evaluate a wide range of process options. During FY09, efforts at ORNL have been focused on two priority tasks toward achieving the IPSC goal: (1) a top-down exploration of architecture - Subtask 1: Explore framework for code development and integration for plant-level simulation; and (2) a bottom-up fundamental modeling effort - Subtask 2: Development of molecular-level agent design code. Subtask 1 is important because definition and development of architecture is a key issue for the overall effort, as selection of an overall approach and code/data requirements is a necessary first step in the organization, design and development of separations and safeguards codes that will be incorporated. The agent design effort of Subtask 2 is a molecular-level modeling effort that has a direct impact on a near-term issue of the Separations and Waste Forms Campaign. A current focus of experimental efforts is the development of robust agents and processes for separation of Am/Cm. Development of enhanced agent-design codes will greatly accelerate discovery and experimental testing.

  1. Contribution of the 'safeguarded' to the development of safeguards

    International Nuclear Information System (INIS)

    Anderson, A.R.

    1977-01-01

    The development of an efficient system of international safeguards requires close and detailed interaction between the safeguarding authority and those being safeguarded, i.e. the plant operator and the State System to which he belongs. Such interaction is found in other control systems but the degree of international collaboration involved in safeguards is perhaps unique and it is valuable to review and analyse the contributions which have arisen from prudent management considerations. The familiar ''Blue Book'' (INFCIRC 153) recognizes clearly the need for an effective State's System of accounting for and control of nuclear materials as a necessary pre-requisite for the development and implementation of an effective IAEA system of safeguards. It is therefore helpful to summarize the relevant contributions from the 'safeguarded' in terms of the components of the State's System specified in paragraph 32 of the Blue Book. This paper reviews the continuing contributions stemming from plant and national experience, with particular emphasis on the development of measurement systems and physical inventory procedures relevant to safeguards. Attention is also drawn to those areas where the specific objectives of IAEA Safeguards lead to requirements additional to those required for management purposes. (author)

  2. Safeguards training at Pacific Northwest Laboratory

    International Nuclear Information System (INIS)

    Dickman, D.A.

    1988-01-01

    In recent years considerable attention has been given to upgrading security education programs at facilities across the country. At Pacific Northwest Laboratory (PNL), a Laboratory-wide Safeguard Awareness Training Program has been established in order to raise the cognizance of the entire staff with regard to safeguards issues and concerns. This aggressive safeguards program involves a strong interface of physical security measure and material control and accountability systems. Within PNL, four distinct audiences were defined and a needs assessment analysis performed for each to determine specific training requirements. The target audiences identified were: material balance area (MBA) custodians, managers of material balance areas, material handlers, and new employees. Five safeguards training courses were created to meet the needs of those audiences. This paper discusses the development of the Safeguards Awareness Program at PNL and its benefits to the Laboratory

  3. Nuclear safeguards implementations in Taiwan

    International Nuclear Information System (INIS)

    Hou, R-H.; Chang, C-K.; Lin, C-R.; Gone, J-K.; Chen, W-L.; Yao, D.

    2006-01-01

    Full text: Now with six Nuclear Power Plant (NPP) units in operation, two Advanced Boiling Water Reactor (ABWR) units under construction, and other peaceful applications of nuclear and radiation technology expanding in great pace, the Atomic Energy Council (AEC) has been focused on reactor safety regulation, radiation protection, radioactive waste administration, environmental monitoring and R and D for technology development and other civilian nuclear applications. Despite Taiwan's departure from the United Nations and therefore its family member International Atomic Energy Agency (IAEA) in 1971, Taiwan remains its commitment to the Treaty on the Non-Proliferation of Nuclear Weapons (NPT). To date, Taiwan is still part of the international nuclear safeguards system and accepts IAEA's inspections in accordance with its regulations on nuclear safeguards. In 1998, Taiwan further agreed, through exchange of letters between the AEC and IAEA, to implementation of the measures provided for in the model Protocol Additional to its safeguards agreement. In this paper, we will introduce Taiwan's nuclear safeguards history and describe some highlights of safeguards implementation in recent years, such as complementary accesses, transparency visits, remote monitoring inspections, unannounced inspections, facility attachment termination for the decommissioned facilities, and annual safeguards implementation meeting with IAEA

  4. 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)

  5. International safeguards 1979

    International Nuclear Information System (INIS)

    Fischer, D.

    1979-01-01

    First, the nature of the nuclear proliferation problem is reviewed. Afterward, the extent to which the risk of further horizontal proliferation of nuclear weapons is being contained by international agreements and by the application of the IAEA's safeguards under these agreements is investigated. The geographical scope of such safeguards, the gaps in safeguards coverage, and the political and technical effectiveness of such safeguards are examined. In conclusion, it is pointed out that IAEA safeguards are the cutting edge of almost every nonproliferation measure that has so far been applied or put forward. Safeguards would also play a part in any international scheme for limiting vertical proliferation. If the cutting edge of safeguards is blunted or if, for one reason or another, safeguards cannot be or are not being applied, the nonproliferation regime will suffer commensurate damage

  6. Contribution of the ''safeguarded'' to the development of safeguards

    International Nuclear Information System (INIS)

    Anderson, A.R.

    1977-01-01

    The development of an efficient system of international safeguards requires close and detailed interaction between the safeguarding authority and those being safeguarded, i.e. the plant operator and the State System to which he belongs. Such interaction is found in other control systems but the degree of international collaboration involved in Safeguards is perhaps unique and it is valuable to review and analyse the contributions which have arisen from prudent management considerations. Management has many reasons to exercise stringent control of nuclear materials stemming from the value and hazardous nature of the materials being used, and the requirements of relevant national legislation. Because systems at a plant and within a State are generally designed to control quantities of nuclear materials within limits smaller than those specified in the I.A.E.A.'s Safeguards objectives, experience at the plant level has contributed significantly to the development of International Safeguards procedures. In making such contributions, plant management and the national authorities have a common objective with that of the I.A.E.A. in developing a Safeguards system which is both technically-effective and cost-effective. The pursuit of this objective requires that implementation of the Safeguards system can be modified in the light of relevant practical experience of plant operators and of the I.A.E.A. The familiar Blue Book (INFCIRC 153) recognises clearly the need for an effective State's System of accounting for and control of nuclear materials as a necessary pre-requisite for the development and implementation of an effective I.A.E.A. system of Safeguards. It is therefore helpful to review the relevant contributions from the 'Safeguarded' in terms of the components of the State's System specified in paragraph 32 of the Blue Book. This paper reviews the continuing contributions stemming from plant and national experience, with particular emphasis on the development of

  7. The Safeguards Analytical Laboratory (SAL) in the Agency's safeguards measurement system activity in 1990

    International Nuclear Information System (INIS)

    Bagliano, G.; Cappis, J.; Deron, S.; Parus, J.L.

    1991-05-01

    The IAEA applies Safeguards at the request of a Member State to whole or part of its nuclear materials. The verification of nuclear material accountability still constitutes the fundamental method of control, although sealing and surveillance procedures play an important complementary and increasing role in Safeguards. A small fraction of samples must still be analyzed at independent analytical laboratories using conventional Destructive Analytical (DA) methods of highest accuracy in order to verify that small potential biases in the declarations of the State are not masking protracted diversions of significant quantities of fissile materials. The Safeguards Analytical Laboratory (SAL) is operated by the Agency's Laboratories at Seibersdorf to provide to the Department of Safeguards and its inspectors such off-site Analytical Services, in collaboration with the Network of Analytical Laboratories (NWAL) of the Agency. In the last years SAL and the Safeguards DA Services have become more directly involved in the qualification and utilization of on-site analytical instrumentation such as K-edge X-Ray absorptiometers and quadrupole mass spectrometers. The nature and the origin of the samples analyzed, the measurements usually requested by the IAEA inspectors, the methods and the analytical techniques available at SAL and at the Network of Analytical Laboratories (NWAL) with the performances achieved during the past years are described and discussed in several documents. This report gives an evaluation compared with 1989 of the volume and the quality of the analyses reported in 1990 by SAL and by the NWAL in reply to requests of IAEA Safeguards inspectors. The reports summarizes also on-site DA developments and support provided by SAL to the Division of Safeguards Operation and special training courses to the IAEA Safeguards inspectors. 55 refs, 7 figs, 15 tabs

  8. Goals of measurement systems for international safeguards

    International Nuclear Information System (INIS)

    de Montmollin, J.M.; Weinstock, E.V.

    1979-01-01

    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

  9. The U.S./IAEA Workshop on Software Sustainability for Safeguards Instrumentation: Report to the NNSA DOE Office of International Nuclear Safeguards (NA-241)

    Energy Technology Data Exchange (ETDEWEB)

    Pepper, Susan E. [Brookhaven National Lab. (BNL), Upton, NY (United States); Pickett, Chris A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Queirolo, Al [Brookhaven National Lab. (BNL), Upton, NY (United States); Bachner, Katherine M. [Brookhaven National Lab. (BNL), Upton, NY (United States); Worrall, Louise G. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-04-07

    The U.S Department of Energy (DOE) National Nuclear Security Administration (NNSA) Next Generation Safeguards Initiative (NGSI) and the International Atomic Energy Agency (IAEA) convened a workshop on Software Sustainability for Safeguards Instrumentation in Vienna, Austria, May 6-8, 2014. Safeguards instrumentation software must be sustained in a changing environment to ensure existing instruments can continue to perform as designed, with improved security. The approaches to the development and maintenance of instrument software used in the past may not be the best model for the future and, therefore, the organizers’ goal was to investigate these past approaches and to determine an optimal path forward. The purpose of this report is to provide input for the DOE NNSA Office of International Nuclear Safeguards (NA-241) and other stakeholders that can be utilized when making decisions related to the development and maintenance of software used in the implementation of international nuclear safeguards. For example, this guidance can be used when determining whether to fund the development, upgrade, or replacement of a particular software product. The report identifies the challenges related to sustaining software, and makes recommendations for addressing these challenges, supported by summaries and detailed notes from the workshop discussions. In addition the authors provide a set of recommendations for institutionalizing software sustainability practices in the safeguards community. The term “software sustainability” was defined for this workshop as ensuring that safeguards instrument software and algorithm functionality can be maintained efficiently throughout the instrument lifecycle, without interruption and providing the ability to continue to improve that software as needs arise.

  10. The U.S./IAEA Workshop on Software Sustainability for Safeguards Instrumentation: Report to the NNSA DOE Office of International Nuclear Safeguards (NA-241)

    International Nuclear Information System (INIS)

    Pepper, Susan E.; Pickett, Chris A.; Queirolo, Al; Bachner, Katherine M.; Worrall, Louise G.

    2015-01-01

    The U.S Department of Energy (DOE) National Nuclear Security Administration (NNSA) Next Generation Safeguards Initiative (NGSI) and the International Atomic Energy Agency (IAEA) convened a workshop on Software Sustainability for Safeguards Instrumentation in Vienna, Austria, May 6-8, 2014. Safeguards instrumentation software must be sustained in a changing environment to ensure existing instruments can continue to perform as designed, with improved security. The approaches to the development and maintenance of instrument software used in the past may not be the best model for the future and, therefore, the organizers' goal was to investigate these past approaches and to determine an optimal path forward. The purpose of this report is to provide input for the DOE NNSA Office of International Nuclear Safeguards (NA-241) and other stakeholders that can be utilized when making decisions related to the development and maintenance of software used in the implementation of international nuclear safeguards. For example, this guidance can be used when determining whether to fund the development, upgrade, or replacement of a particular software product. The report identifies the challenges related to sustaining software, and makes recommendations for addressing these challenges, supported by summaries and detailed notes from the workshop discussions. In addition the authors provide a set of recommendations for institutionalizing software sustainability practices in the safeguards community. The term ''software sustainability'' was defined for this workshop as ensuring that safeguards instrument software and algorithm functionality can be maintained efficiently throughout the instrument lifecycle, without interruption and providing the ability to continue to improve that software as needs arise.

  11. Design and evaluation of an integrated safeguards system: principles

    International Nuclear Information System (INIS)

    Markin, J.T.; Coulter, C.A.; Gutmacher, R.G.; Whitty, W.J.

    1984-01-01

    An integrated safeguards system is defined as a collection of safeguards activities in which system components are coordinated to meet safeguards objectives efficiently within constraints imposed by safeguards resources, facility operations, potential adversaries, and regulatory requirements. This paper describes principles for designing and evaluating an integrated safeguards system that consists of four parts: a problem definition phase that specifies resources and constraints composing the problem boundary values, a system analysis/synthesis phase that describes how to select and integrate safeguards activities for efficient attainment of system objectives, a system evaluation/optimization phase that defines measures of safeguards performance and develops methods for evaluating them, and a decision-making phase that develops principles for selecting admissible designs and preference-ordering designs

  12. IAEA safeguards instrumentation: Development, implementation and control

    International Nuclear Information System (INIS)

    Rundquist, D.E.

    1983-01-01

    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)

  13. The basis for the strengthening of safeguards

    International Nuclear Information System (INIS)

    Goldschmidt, P.

    1999-01-01

    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)

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

    International Nuclear Information System (INIS)

    Kempf, C.R.

    1994-01-01

    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. The next generation safeguards initiative

    International Nuclear Information System (INIS)

    Tobey, William

    2008-01-01

    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

  16. Safeguards

    International Nuclear Information System (INIS)

    Carchon, R.

    1998-01-01

    Safeguards activities at the Belgian Nuclear Research Centre SCK/CEN answer internal needs, support the Belgian authorities, and support the IAEA. The main objectives of activities concerning safeguards are: (1) to contribute to a prevention of the proliferation of nuclear materials by maintaining an up-to-date expertise in the field of safeguards and providing advice and guidance as well as scientific and technical support to the Belgian authorities and nuclear industry; (2) to improve the qualification and quantification of nuclear materials via nondestructive assay. The main achievements for 1997 are described

  17. Fuel cycle based safeguards

    International Nuclear Information System (INIS)

    De Montmollin, J.M.; Higinbotham, W.A.; Gupta, D.

    1985-07-01

    In NPT safeguards the same model approach and absolute-quantity inspection goals are applied at present to all similar facilities, irrespective of the State's fuel cycle. There is a continuing interest and activity on the part of the IAEA in new NPT safeguards approaches that more directly address a State's nuclear activities as a whole. This fuel cycle based safeguards system is expected to a) provide a statement of findings for the entire State rather than only for individual facilities; b) allocate inspection efforts so as to reflect more realistically the different categories of nuclear materials in the different parts of the fuel cycle and c) provide more timely and better coordinated information on the inputs, outputs and inventories of nuclear materials in a State. (orig./RF) [de

  18. Design and evaluation of an integrated safeguards system: principles

    International Nuclear Information System (INIS)

    Markin, J.T.; Coulter, C.A.; Gutmacher, R.G.; Whitty, W.J.

    1984-07-01

    An integrated safeguards system is defined as a collection of safeguards activities in which system components are coordinated to meet safeguards objectives efficiently within constraints imposed by safeguards resources, facility operations, potential adversaries, and regulatory requirements. This paper describes principles for designing and evaluating an integrated safeguards system that consists of four parts: (1) a problem definition phase that specifies resources and constraints composing the problem boundary values; (2) a system analysis/synthesis phase that describes how to select and integrate safeguards activities for efficient attainment of system objectives; (3) a system evaluation/optimization phase that defines measures of safeguards performance and develops methods for evaluating them; and (4) a decision-making phase that develops principles for selecting admissible designs and preference-ordering designs. 6 references, 4 figures, 5 tables

  19. Safeguards activities in Japan

    International Nuclear Information System (INIS)

    Osabe, Takeshi

    1998-01-01

    Current Japanese State System for Accountancy and Control (SSAC) has been developing and fully satisfies requirements of both IAEA Safeguards and bilateral partners. However, the public attention on the national and international safeguards activities were increased and the safeguards authorities were required to promote the objective assessment of safeguards implementation to avoid mistrust in safeguards activities which directly influence the public acceptance of nuclear energy in itself. Additionally, since Japan has promoted to complete nuclear fuel cycle including spent fuel reprocessing, enrichment and mixed oxide fuel fabrication this would require further assurance of Japanese non-proliferation commitment. Japan supports the introduction of strengthened safeguards. In this context it is particularly important to strengthen the relationship between national and the IAEA safeguards to contribute actively to the IAEA safeguards in development and utilization of new technologies towards more effective and efficient IAEA safeguards

  20. The IAEA safeguards information system

    International Nuclear Information System (INIS)

    Gmelin, W.R.; Parsick, R.

    1976-01-01

    The IAEA safeguards under the Non-Proliferation Treaty is meant to follow the model agreement developed by the Safeguards Committee in 1970 and formulated in document INFCIRC/153, which contains provisions that Member States, having concluded Safeguards Agreements with the Agency, should provide design information and reports on initial inventories, changes in the inventories and material balances in respect of each nuclear facility and material balance area for all nuclear materials subject to safeguards. The Agency, on the other hand, should establish and maintain an accountancy system which would provide the data on the location and the movements of all nuclear material subject to safeguards on the basis of the reported information and information obtained during inspections in order to support the Agency's verification activities in the field, to enable the preparation of safeguards statements and to adjust the inspection intensity. Following these requirements, a computer-based information system has been developed and is being implemented and used routinely for input manipulations and queries on a limited scale. This information system comprises two main parts: Part 1 for processing the information as provided by the States, and Part 2 (still under development) for processing the inspection data obtained during verification. This paper describes the characteristics of the Agency information system for processing data under the Non-Proliferation Treaty as well as recent operational experience. (author)

  1. A model independent safeguard against background mismodeling for statistical inference

    Energy Technology Data Exchange (ETDEWEB)

    Priel, Nadav; Landsman, Hagar; Manfredini, Alessandro; Budnik, Ranny [Department of Particle Physics and Astrophysics, Weizmann Institute of Science, Herzl St. 234, Rehovot (Israel); Rauch, Ludwig, E-mail: nadav.priel@weizmann.ac.il, E-mail: rauch@mpi-hd.mpg.de, E-mail: hagar.landsman@weizmann.ac.il, E-mail: alessandro.manfredini@weizmann.ac.il, E-mail: ran.budnik@weizmann.ac.il [Teilchen- und Astroteilchenphysik, Max-Planck-Institut für Kernphysik, Saupfercheckweg 1, 69117 Heidelberg (Germany)

    2017-05-01

    We propose a safeguard procedure for statistical inference that provides universal protection against mismodeling of the background. The method quantifies and incorporates the signal-like residuals of the background model into the likelihood function, using information available in a calibration dataset. This prevents possible false discovery claims that may arise through unknown mismodeling, and corrects the bias in limit setting created by overestimated or underestimated background. We demonstrate how the method removes the bias created by an incomplete background model using three realistic case studies.

  2. Improving the Transparency of IAEA Safeguards Reporting

    International Nuclear Information System (INIS)

    Toomey, Christopher; Hayman, Aaron M.; Wyse, Evan T.; Odlaug, Christopher S.

    2011-01-01

    In 2008, the Standing Advisory Group on Safeguards Implementation (SAGSI) indicated that the International Atomic Energy Agency's (IAEA) Safeguards Implementation Report (SIR) has not kept pace with the evolution of safeguards and provided the IAEA with a set of recommendations for improvement. The SIR is the primary mechanism for providing an overview of safeguards implementation in a given year and reporting on the annual safeguards findings and conclusions drawn by the Secretariat. As the IAEA transitions to State-level safeguards approaches, SIR reporting must adapt to reflect these evolutionary changes. This evolved report will better reflect the IAEA's transition to a more qualitative and information-driven approach, based upon State-as-a-whole considerations. This paper applies SAGSI's recommendations to the development of multiple models for an evolved SIR and finds that an SIR repurposed as a 'safeguards portal' could significantly enhance information delivery, clarity, and transparency. In addition, this paper finds that the 'portal concept' also appears to have value as a standardized information presentation and analysis platform for use by Country Officers, for continuity of knowledge purposes, and the IAEA Secretariat in the safeguards conclusion process. Accompanying this paper is a fully functional prototype of the 'portal' concept, built using commercial software and IAEA Annual Report data.

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

    International Nuclear Information System (INIS)

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

    2009-01-01

    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

  4. 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

  5. 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.

  6. 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

  7. Safeguards effectiveness evaluations in safeguards planning

    International Nuclear Information System (INIS)

    Al-Ayat, R.A.

    1987-01-01

    This paper describes analytic tools we developed to quantify the effectiveness of safeguards against theft of special nuclear material by insiders. These tools help identify vulnerabilities in existing safeguards, suggest potential improvements, and help assess the benefits of these upgrades prior to implementation. Alone, these tools are not sufficient for safeguards planning, since the cost of implementing all suggested upgrades almost always exceeds the available resources. This paper describes another tool we developed to allow comparsion of benefits of various upgrades to identify those upgrade packages that achieve the greatest improvement in protection for a given cost and to provide a priority ranking among cost-effective packages, thereby helping decision-makers select the upgrades to implement and highlight the mount of residual risk. 5 refs., 3 figs

  8. Nuclear Safeguards Culture

    International Nuclear Information System (INIS)

    Findlay, T.

    2015-01-01

    The paper will consider safeguards culture both at the IAEA and among member states. It will do so through the lens of organizational culture theory and taking into account developments in safeguards since the Iraq case of the early 1990s. The study will seek to identify the current characteristics of safeguards culture and how it has evolved since the 93+2 programme was initiated, as well as considering the roles of the most important purveyors of such culture, including member states and their national safeguards authorities, the General Conference and Board of Governors, the Director General, the Secretariat as a whole, the Safeguards Department and the inspectorate. The question of what might be an optimal safeguards culture at the Agency and among member states will be investigated, along with the issue of how such a culture might be engendered or encouraged. (author)

  9. Performance Evaluation of New Generation CdZnTe Detectors for Safeguards Applications

    International Nuclear Information System (INIS)

    Ivanovs, V.; Mintcheva, J.; Berlizov, A.; Lebrun, A.

    2015-01-01

    Cadmium zinc telluride detectors (CdZnTe) have found a wide application in nondestructive assay measurements in the IAEA's verification practice. It is because of their form factor, usability, sensitivity and good spectral characteristics that they are extensively used for fresh and spent fuel attribute test measurements. Until now, the series of CdZnTe detectors utilized in the IAEA have covered the range of 5 mm 3 , 20 mm 3 , 60 mm 3 and 500mm 3 of sensitive volume. Recently, new CdZnTe detectors with improved spectroscopic characteristics and significantly bigger active volume have become available, owing to advances in crystal and detector manufacturing and signal processing technologies. The distinctive feature of this new technological development is the application of a low-intensity monochromatic optical stimulation with infrared (IR) light. The use of IR illumination with a properly chosen wavelength close to the absorption edge of the CdZnTe can significantly improve the performance of the detectors. Recognizing potential benefits of these detectors in safeguards applications, the IAEA has performed an evaluation of their performance characteristics. Under evaluation were several new detectors with sensitive volumes of 500 mm 3 , 1500 mm 3 and 4000 mm 3 , as well as all-in-one 60 mm 3 , 500 mm 3 and 1500 mm 3 integrated micro-spectrometers available from RITEC, Latvia. In addition to the standard performance characteristics, such as energy resolution, peak shape, efficiency, linearity, throughput and temperature stability, the potential use of the detectors for safeguards specific measurements, such as uranium enrichment with infinite thickness method, was of particular interest. The paper will describe the advances in the CdZnTe detector technology and present the results of their performance evaluation. (author)

  10. Status of safeguards instrumentation

    International Nuclear Information System (INIS)

    Higinbotham, W.A.

    The International Atomic Energy Agency is performing safeguards at some nuclear power reactors, 50 bulk processing facilities, and 170 research facilities. Its verification activities require the use of instruments to measure nuclear materials and of surveillance instruments to maintain continuity of knowledge of the locations of nuclear materials. Instruments that are in use and under development to measure weight, volume, concentration, and isotopic composition of nuclear materials, and the major surveillance instruments, are described in connection with their uses at representative nuclear facilities. The current status of safeguards instrumentation and the needs for future development are discussed

  11. Implementing Safeguards-by-Design

    International Nuclear Information System (INIS)

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

    2010-01-01

    analysis can be a useful tool in safeguards design. (3) An important obstacle to straight forward application of life-cycle cost analysis is that there is no single organization responsible for the entire life-cycle cost of the facility. (4) The Safeguards Effectiveness Report (SGER) is proposed as a focus for the safeguards design activities, and is intended to be a living document that contains increasing safeguards relevant scope and content as the facility design emerges. Further work is required in a number of areas. The authors note that other studies supported by NGSI are addressing the development of requirements and performance criteria, as well as contributing to the design toolkit through the development of technology, methodology, and safeguards guidelines for designers. With respect to further development of the SBD design process, the authors recommend: (1) In the short term, conduct a workshop with interested industry representatives, to ensure that their perspectives and needs are factored into further development. (2) In the short term, provide NGSI SBD project documents to IAEA, and support them in the conduct of an 'SBD Workshop II.' (3) In the medium term, continue to support the SBD demonstration work started with the Next Generation Nuclear Plant project. (4) In the longer term, conduct further studies to examine the integration of SBD into projects with concurrent consideration of physical security and safety.

  12. Safeguards in the Slovak Republic

    International Nuclear Information System (INIS)

    Vaclav, J.

    2010-01-01

    The former Czechoslovakia acceded to the Non-Proliferation Treaty in 1968. Based on requirements of the Safeguard Agreement the State System of Accounting for and Control of nuclear material has been established. After dissolution of Czechoslovakia the Slovak Republic succeeded to the Safeguards Agreement. As a regulator the Nuclear Regulatory Authority of the Slovak Republic (UJD) has been constituted. After European Union (EU) accession EU legislation became valid in the Slovak republic. Atomic Law No. 541/2004 Coll. on Peaceful Use of Nuclear Energy adopts this legislation. In the frame of strengthening the IAEA safeguards an implementation of the Protocol Additional became actual. The Protocol Additional was signed by the government of the Slovak Republic in September 1999. On 1 December 2005 safeguards agreement INFCIRC/193 including the relevant Additional Protocol entered into force. As an instrument supporting non-proliferation of nuclear weapons a control of export/import of nuclear material, nuclear related and dual-use material following the EC regulation 428/2009 of 5 May 2009 setting up a Community regime for the control of exports, transfer, brokering and transit of dual use items. The execution of accountancy and control of nuclear material inspection activities has been considerably influenced by the implementation of integrated safeguards, implemented in the Slovak Republic on 1 September 2009. The aim of mentioned integrated safeguards regime is to decrease the amount and difficulty of inspections. At the same time the possibility of accountancy and control of nuclear material inspections announced 24 hours in advance took effect. The execution of Protocol Additional inspections remains the same. Additionally to international safeguards system UJD has kept the national safeguards system which observes all nuclear material on the territory of the Slovak Republic. The government of the Slovak Republic plays active role within activities of the NSG

  13. Safeguards '85

    International Nuclear Information System (INIS)

    Gruemm, H.

    1981-01-01

    IAEA safeguards watch over the pledge of those non-nuclear weapon countries, which are signatories to the NPT, to refrain from using nuclear installations for military purposes. At present, some 700 installations are inspected in 50 countries, among them 117 nuclear power plants. Further advancement of these safeguards measures serves to develop new methods and equipment for safeguards inspection, ensure that the growing numbers of new plants are inspected, and achieve complete coverage of the eleven countries not signatories to the NPT. However, the long term effectiveness of safeguards will depend on progress being made in the contractual obligations fur nuclear disarmament and in assuring the continuity of supply to non-nuclear weapon countries by the atomic powers and the supplier countries. (orig.) [de

  14. IAEA safeguards

    International Nuclear Information System (INIS)

    1985-01-01

    IAEA safeguards are a system of technical measures within the framework of international non-proliferation policy entrusted to the IAEA in its Statute and by other treaties. About 98% of the world's nuclear installations outside the nuclear-weapon countries are now under safeguards. This paper gives a review of IAEA activities in this field: objectives, agreements, work and development of staff of the IAEA's Department of Safeguards, instruments and techniques for direct measurement and verification of nuclear material. (author)

  15. Assessment of ambient-temperature, high-resolution detectors for nuclear safeguards applications

    International Nuclear Information System (INIS)

    Ruhter, W.D.; McQuaid, J.H.; Lavietes, A.

    1993-01-01

    High-resolution, gamma- and x-ray spectrometry are used routinely in nuclear safeguards verification measurements of plutonium and uranium in the field. These measurements are now performed with high-purity germanium (HPGe) detectors that require cooling liquid-nitrogen temperatures, thus limiting their utility in field and unattended safeguards measurement applications. Ambient temperature semiconductor detectors may complement HPGe detectors for certain safeguards verification applications. Their potential will be determined by criteria such as their performance, commercial availability, stage of development, and costs. We have conducted as assessment of ambient temperature detectors for safeguards measurement applications with these criteria in mind

  16. 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.

  17. On-line safeguards design: an application of estimation/detection

    International Nuclear Information System (INIS)

    Candy, J.V.; Dunn, D.R.; Rozsa, R.B.

    1979-01-01

    The applicability of madern signal processing techniques to the safeguards problem for a plutonium nitrate storage tank and concentrator is addressed. The techniques involve mathematical modeling, optimal estimation of process variables, and the detection of abnormal changes in these variables due to adversary diversion. The performance of these techniques is preesented for various diversion scenarios

  18. Safeguards on nuclear waste

    International Nuclear Information System (INIS)

    Crawford, D.W.

    1995-01-01

    Safeguards and security policies within the Department of Energy (DOE) have been implemented in a graded fashion for the protection, control and accountability of nuclear materials. This graded philosophy has meant that safeguards on low-equity nuclear materials, typically considered of low diversion attractiveness such as waste, has been relegated to minimal controls. This philosophy has been and remains today an acceptable approach for the planning and implementation of safeguards on this material. Nuclear waste protection policy and guidance have been issued due to a lack of clear policy and guidance on the identification and implementation of safeguards controls on waste. However, there are issues related to safe-guarding waste that need to be clarified. These issues primarily stem from increased budgetary and resource pressures to remove materials from safeguards. Finally, there may be an unclear understanding, as to the scope and content of vulnerability assessments required prior to terminating safeguards on waste and other discardable materials and where the authority should lie within the Department for making decisions regarding safeguards termination. This paper examines these issues and the technical basis for Departmental policy for terminating safeguards on waste

  19. Safeguarding the atom

    International Nuclear Information System (INIS)

    Fischer, D.; Szasz, P.

    1985-01-01

    Safeguards play a key role in verifying the effectiveness of restraints on the spread of nuclear weapons. This book is a study of the safeguards system of the International Atomic Energy Agency, an important element of the non-proliferation regime. It focuses on the politics of safeguards, especially the political problems of the IAEA and of the day-to-day application of safeguards. It contains a critical appraisal and proposals for ways of improving existing procedures and of adapting them to the political and technological changes of recent years. IAEA safeguards represent the world's first and so far only attempt to verify an arms control agreement by systematic on-site inspection, and their applicability to other arms control measures is examined. (author)

  20. SAFEGUARDS ENVELOPE: PREVIOUS WORK AND EXAMPLES

    International Nuclear Information System (INIS)

    Metcalf, Richard; Bevill, Aaron; Charlton, William; Bean, Robert

    2008-01-01

    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

  1. Inventory of safeguards software

    International Nuclear Information System (INIS)

    Suzuki, Mitsutoshi; Horino, Koichi

    2009-03-01

    The purpose of this survey activity will serve as a basis for determining what needs may exist in this arena for development of next-generation safeguards systems and approaches. 23 software tools are surveyed by JAEA and NMCC. Exchanging information regarding existing software tools for safeguards and discussing about a next R and D program of developing a general-purpose safeguards tool should be beneficial to a safeguards system design and indispensable to evaluate a safeguards system for future nuclear fuel facilities. (author)

  2. SNAP/SOS: a package for simulating and analyzing safeguards systems

    International Nuclear Information System (INIS)

    Grant, F.H. III; Polito, J.; Sabuda, J.

    1983-01-01

    The effective analysis of safeguards systems at nuclear facilities requires significant effort. The Safeguards Network Analysis Procedure (SNAP) and the SNAP Operating System (SOS) reduce that effort to a manageable level. SNAP provides a detailed analysis of site safeguards for tactical evaluation. SOS helps the analyst organize and manage the SNAP effort effectively. SOS provides a database for model storage, automatic model generation, and computer graphics. The SOS/SNAP combination is a working example of a simulation system including executive-level control, database system, and facilities for model creation, editing, and output analysis

  3. 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.

  4. The safeguards options study

    International Nuclear Information System (INIS)

    Hakkila, E.A.; Mullen, M.F.; Olinger, C.T.; Stanbro, W.D.; Olsen, A.P.; Roche, C.T.; Rudolph, R.R.; Bieber, A.M.; Lemley, J.; Filby, E.

    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

  5. Safeguards and nuclear forensics

    International Nuclear Information System (INIS)

    Gangotra, Suresh

    2016-01-01

    Nuclear Safeguards is the 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 deterrence of such diversion by early detection. Safeguards implementation involves nuclear material accounting and containment and surveillance measures. The safeguards are implemented in nuclear facilities by the states, or agencies and International Atomic Energy Agency (IAEA). The measures for the safeguards include nuclear material Accounting (NUMAC) and Containment and surveillance systems. In recent times, there have been advances in safeguards like Near Real Time Monitoring (NRTM), Dynamic Nuclear Material Accounting (DNMA), Safeguards-by-Design (SBD), satellite imagery, information from open sources, remote monitoring etc

  6. IAEA safeguards for geological repositories

    International Nuclear Information System (INIS)

    Moran, B.W.

    2005-01-01

    In September. 1988, the IAEA held its first formal meeting on the safeguards requirements for the final disposal of spent fuel and nuclear material-bearing waste. The consensus recommendation of the 43 participants from 18 countries at this Advisory Group Meeting was that safeguards should not terminate of spent fuel even after emplacement in, and closure of, a geologic repository.' As a result of this recommendation, the IAEA initiated a series of consultants' meetings and the SAGOR Programme (Programme for the Development of Safeguards for the Final Disposal of Spent Fuel in Geologic Repositories) to develop an approach that would permit IAEA safeguards to verify the non-diversion of spent fuel from a geologic repository. At the end of this process, in December 1997, a second Advisory Group Meeting, endorsed the generic safeguards approach developed by the SAGOR Programme. Using the SAGOR Programme results and consultants' meeting recommendations, the IAEA Department of Safeguards issued a safeguards policy paper stating the requirements for IAEA safeguards at geologic repositories. Following approval of the safeguards policy and the generic safeguards approach, the Geologic Repository Safeguards Experts Group was established to make recommendations on implementing the safeguards approach. This experts' group is currently making recommendations to the IAEA regarding the safeguards activities to be conducted with respect to Finland's repository programme. (author)

  7. The Department of Safeguards Quality Management System

    International Nuclear Information System (INIS)

    Konecni, S.

    2015-01-01

    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)

  8. Measuring Safeguards Culture

    International Nuclear Information System (INIS)

    Frazar, Sarah L.; Mladineo, Stephen V.

    2011-01-01

    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.

  9. International safeguards

    International Nuclear Information System (INIS)

    Sanders, B.; Ha Vinh Phuong

    1976-01-01

    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.) [fr

  10. Concept for fuel-cycle based safeguards

    International Nuclear Information System (INIS)

    deMontmollin, J.M.; Higinbotham, W.A.; Gupta, D.

    1985-01-01

    Although the guidelines for NPT safeguards specify that the State's fuel cycle and degree of international independence are to be taken into account, the same model approach and absolute-quantity inspection goals are applied to all similar facilities, irrespective of the State's fuel cycle, and the findings are reported in those terms. A concept whereby safeguards might more effectively and efficiently accomplish the purposes of NPT safeguards is explored. The principal features are: (1) division of the fuel cycle into three zones, each containing material having a different degree of significance for safeguards; (2) closing a verified material balance around each zone, supplementing the present MBA balances for more sensitive facilities and replacing them for others; (3) maintenance by the IAEA of a current book inventory for each facility by means of immediate, abbreviated reporting of interfacility transfers; (4) near real-time analysis of material flow patterns through the fuel cycle; and (5) a periodic statement of the findings for the entire State that takes the form that there is assurance that all nuclear materials under safeguards are accounted for to some stated degree of uncertainty

  11. International safeguards data management system

    International Nuclear Information System (INIS)

    Argentesi, F.; Costantini, L.; Franklin, M.; Dondi, M.G.

    1981-01-01

    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. The Impact of Interdependencies on the Effectiveness and Efficiency of Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Kyriakopoulos, Nicholas [Department of Electrical and Computer Engineering, The George Washington University, Washington, DC (United States)

    2012-06-15

    The purpose of Integrated Safeguards is to evaluate a State as a whole and provide credible assurance of the absence of undeclared nuclear activities. The new system is not viewed as an addition to the traditional safeguards system but as a collection of measures to verify the correctness and completeness of the declarations. The broadening of the scope to evaluate the State for the purpose of enhancing non-proliferation introduces uncertainties that affect the performance of the safeguards system. The processes within a State that Integrated Safeguards seeks to monitor are not clearly defined. Neither are the measurement and evaluation systems for the verification of the absence of undeclared activities. A refinement of the existing diversion process model is needed that takes into account the likelihood that a State would undertake a clandestine program. To develop such a model this paper examines the nuclear programs of seven States that have built or attempted to build nuclear weapons and one that is being accused of having one but denies it. Analysis of the factors that are essential in the decision of a State to embark on a nuclear weapons program indicates leads to the identification of certain indicators for clandestine nuclear weapons programs. It identifies the conditions and interdependencies that most likely lead those States to undertake clandestine weapons programs and develops a set of likelihood indicators that can be used in the application of safeguards to a State as a whole. Existence of serious conflicts involving territorial disputes, transparency in the social system, militarization of the State, and democratization of the political process are the common characteristics of those States. Although these are not easily quantifiable indicators, concepts such as fuzzy logic can be used to construct likelihood estimators for the presence of absence of clandestine programs leading to a State-specific safeguards approach adapted to the conditions of

  13. Integrated Safeguards Information System for Japan (ISIS-J) - Strengthening SSAC for Enhancing Confidence in Compliance with Safeguards Obligations -

    International Nuclear Information System (INIS)

    Iso, S.; Nishiyama, N.; Kumakura, S.; Takizawa, K.; Yoshida, H.; Kobayashi, I.; Kikuchi, M.; Kimura, N.; Matsubara, T.; Yatsu, S.

    2010-01-01

    not only obligatory information by the safeguards agreement and the additional protocol but also technical evaluation results as certain technical evidences with the accuracy and precision level of the declared information by the national analysis, e.g., results of NDA and DA verification, statistical analysis by cross check of operators values with verification results, and confirmation of expanded declaration by open source information, such as technical documents and others. Based on the enhanced findings, the IAEA could carry out advanced and innovative inspections by unattended surveillance system with remote data transmission and random scheduled inspection with unpredictability. Japan would like to show the model of strengthen SSAC function for enhancing confidence under integrated safeguards. (author)

  14. Nuclear safeguards - a system in transition

    International Nuclear Information System (INIS)

    Carlson, J.

    1999-01-01

    'Classical' safeguards have a strong emphasis on nuclear materials accountancy, and are primarily concerned with verifying nuclear activities as declared by the State - what has been termed the correctness of States' declarations. Following the Gulf War, failure to adequately address the possibility of undeclared nuclear activities - the issue of the completeness of States' declarations - has been recognised as a major shortcoming in the classical safeguards system, and major changes are in progress to strengthen the IAEA's capabilities in this regard. Agreement has been reached on a Model Protocol substantially extending the IAEA's authority, and there has been good progress in developing the new approaches and technologies required to ensure this authority is used effectively. IAEA safeguards are undergoing a major transition, towards greater emphasis on information collection and analysis, diversity of verification methods, incorporation of more qualitative judgments, and improved efficiency. These changes present major challenges to the IAEA and to the international community, but the end result will be a more effective safeguards system

  15. Achieving the Benefits of Safeguards by Design

    International Nuclear Information System (INIS)

    Bjornard, Trond; Bean, Robert; Hebditch, David; Morgan, Jim; Meppen, Bruce; DeMuth, Scott; Ehinger, Michael; Hockert, John

    2008-01-01

    The overarching driver for developing a formalized process to achieve safeguards by design is to support the global growth of nuclear power while reducing 'nuclear security' risks. This paper discusses an institutional approach to the design process for a nuclear facility, for designing proliferation resistance, international safeguards and U.S. national safeguards and security into new nuclear facilities. In the United States, the need exists to develop a simple, concise, formalized, and integrated approach for incorporating international safeguards and other non-proliferation considerations into the facility design process. An effective and efficient design process is one which clearly defines the functional requirements at the beginning of the project and provides for the execution of the project to achieve a reasonable balance among competing objectives in a cost effective manner. Safeguards by Design is defined as 'the integration of international and national safeguards, physical security and non-proliferation features as full and equal partners in the design process of a nuclear energy system or facility,' with the objective to achieve facilities that are intrinsically more robust while being less expensive to safeguard and protect. This Safeguards by Design process has been developed such that it: (sm b ullet) Provides improved safeguards, security, and stronger proliferation barriers, while reducing the life cycle costs to the operator and regulatory agencies, (sm b ullet) Can be translated to any international context as a model for nuclear facility design, (sm b ullet) Fosters a culture change to ensure the treatment of 'nuclear security' considerations as 'full and equal' partners in the design process, (sm b ullet) Provides a useful tool for the project manager responsible for the design, construction, and start-up of nuclear facilities, and (sm b ullet) Addresses the key integration activities necessary to efficiently incorporate International Atomic

  16. The evolution of IAEA safeguards

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-11-01

    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

  17. The evolution of IAEA safeguards

    International Nuclear Information System (INIS)

    1998-01-01

    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

  18. Regional safeguards arrangements: The Argentina-Brazil experience

    International Nuclear Information System (INIS)

    Marzo, M.; Gonzales, H.L.; Iskin, M.C.L.; Vicens, H.

    1997-01-01

    A Common System of Accounting and Control of Nuclear Material (SCCC) was established by Argentina and Brazil in July 1992. It is a full scope safeguard's system in both countries. The Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC) was created to apply the SCCC. The main elements of the SCCC are presented. The main safeguards' procedures are described. A brief discussion of the inspection methodology and its impact for facility operators is performed. The safeguard's implementation from the operator's point of view is commented, taking as example a fuel fabrication plant in Argentina and a uranium enrichment plant in Brazil. (author)

  19. Some problems relating to application of safeguards in the future

    International Nuclear Information System (INIS)

    Tolchenkov, D.L.

    1983-01-01

    By the end of this century there will have been a considerable increase in the amount of nuclear material and the number of facilities subject to IAEA safeguards. The IAEA will therefore be faced with problems due to the increased volume of safeguards activity, the application of safeguards to new types of facility and to large facilities, the optimization of the existing IAEA safeguards system and so on. The authors analyse the potential growth in the IAEA's safeguards activities up to the year 2000 and consider how to optimize methods for the application of safeguards, taking into account a number of factors relating to a State's nuclear activity, the application of full-scope IAEA safeguards etc. On the basis of a hypothetical model of the nuclear fuel cycle that allows for the factors considered as part of the International Nuclear Fuel Cycle Evaluation (INFCE), the authors assess the possible risk of diversion as a function of a full-scope safeguards effort. They also examine possible conceptual approaches to safeguarding large-scale facilities such as fuel reprocessing and uranium enrichment plants. (author)

  20. The 50 Years of Safeguards and Non-Proliferation in Poland

    International Nuclear Information System (INIS)

    Pawlak, A.; Jurkowski, M.; Zagrajek, M.

    2015-01-01

    Milestones of safeguards and non-proliferation activities are presented. Poland has declared its compliance with non-proliferation regime by ratification of Treaty of Nonproliferation of Nuclear Weapons in 1969. Poland concluded in 1972 Agreement with IAEA for application of safeguards — INFCIRC/153. Next steps in implementation of international safeguards were: ratification of Additional Protocol and introduction of Integrated Safeguards. After accession to European Union, Poland fulfils its safeguards obligations according to following international legal instruments: Treaty establishing Euratom, Agreement between Poland, European Commission and International Atomic Energy Agency in connection with implementation of Article III of Treaty of Non-proliferation of Nuclear Weapons — INFCIRC/193 and Additional Protocol to this Agreement — INFCIRC/193 Add.8. Detailed safeguards requirements are established by domestic Act of Parliament of 29th November 2000 — Atomic law and European Union's Regulations of Commission (Euratom) No 302/2005 on application of Euratom safeguards and the Commission Recommendation on guidelines for the application of Regulation (Euratom) No 302/2005. SSAC was established in 1972 as required by CSA. Activities related to accounting for and control of nuclear material were conducted from 1970s till 1990s by Central Laboratory for Radiological Protection and National Inspectorate for Radiation and Nuclear Safety. Currently, NAEA is responsible for collecting and maintenance of accounting data and safeguards inspections at all MBAs. Around 30 routine inspections/year are performed by the NAEA, Euratom and IAEA. In addition, usually 2 unannounced inspections/year under framework of Integrated Safeguards are conducted. In accordance with implementation of Global Threat Reduction Initiative seven shipments of high enriched nuclear fuel from research reactor to Russian Federation under supervision of safeguards inspectors from NAEA

  1. 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.

  2. Model protocol additional to the agreement(s) between state(s) and the International Atomic Energy Agency for the application of safeguards

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    This document is a model Additional Protocol designed for States having a Safeguards Agreement with the Agency, in order to strengthen the effectiveness and improve the efficiency of the safeguard system as a contribution to global nuclear non-proliferation objectives.

  3. Model Protocol Additional to the Agreement(s) between State(s) and the International Atomic Energy Agency for the application of safeguards

    International Nuclear Information System (INIS)

    1998-12-01

    This document is a model Additional Protocol designed for States having a Safeguards Agreement with the Agency, in order to strengthen the effectiveness and improve the efficiency of the safeguards system as a contribution to global nuclear non-proliferation objectives

  4. Model protocol additional to the agreement(s) between state(s) and the International Atomic Energy Agency for the application of safeguards

    International Nuclear Information System (INIS)

    1997-09-01

    This document is a model Additional Protocol designed for States having a Safeguards Agreement with the Agency, in order to strengthen the effectiveness and improve the efficiency of the safeguard system as a contribution to global nuclear non-proliferation objectives

  5. 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.

  6. Performance values for non destructive assay (NDA) techniques applied to safeguards: the 2002 evaluation by the ESARDA NDA Working Group

    International Nuclear Information System (INIS)

    Guardini, S.

    2003-01-01

    The first evaluation of NDA performance values undertaken by the ESARDA Working Group for Standards and Non Destructive Assay Techniques (WGNDA) was published in 1993. Almost 10 years later the Working Group decided to review those values, to report about improvements and to issue new performance values for techniques which were not applied in the early nineties, or were at that time only emerging. Non-Destructive Assay techniques have become more and more important in recent years, and they are used to a large extent in nuclear material accountancy and control both by operators and control authorities. As a consequence, the performance evaluation for NDA techniques is of particular relevance to safeguards authorities in optimising Safeguards operations and reducing costs. Performance values are important also for NMAC regulators, to define detection levels, limits for anomalies, goal quantities and to negotiate basic audit rules. This paper presents the latest evaluation of ESARDA Performance Values (EPVs) for the most common NDA techniques currently used for the assay of nuclear materials for Safeguards purposes. The main topics covered by the document are: techniques for plutonium bearing materials: PuO 2 and MOX; techniques for U-bearing materials; techniques for U and Pu in liquid form; techniques for spent fuel assay. This issue of the performance values is the result of specific international round robin exercises, field measurements and ad hoc experiments, evaluated and discussed in the ESARDA NDA Working Group. (author)

  7. The international safeguards system and physical protection

    International Nuclear Information System (INIS)

    Canty, M.J.; Lauppe, W.D.; Richter, B.; Stein, G.

    1990-02-01

    The report summarizes and explains facts and aspects of the IAEA safeguards performed within the framework of the Non-Proliferation Treaty, and shows perspectives to be discussed by the NPT Review Conferences in 1990 and 1995. The technical background of potential misuse of nuclear materials for military purposes is explained in connection with the physical protection regime of the international safeguards, referring to recent developments for improvement of technical measures for material containment and surveillance. Most attention is given to the peaceful uses of nuclear energy and their surveillance by the IAEA safeguards, including such new technologies and applications as controlled nuclear fusion, laser techniques for uranium enrichment, and particle accelerators. The report's concluding analyses of the current situation show potentials for improvement and desirable or necessary consequences to be drawn for the international safeguards system, also taking into account recent discussions on the parliamentary level. (orig./HP) [de

  8. Integrated safeguards: Australian views and experience

    International Nuclear Information System (INIS)

    Carlson, J.; Bragin, V.; Leslie, R.

    2001-01-01

    Full text: Australia has had a pioneering role in assisting the IAEA to develop the procedures and methods for strengthened safeguards, both before and after the conclusion of Australia's additional protocol. Australia played a key role in the negotiation of the model additional protocol, and made ratification a high priority in order to encourage early ratification by other States. Australia was the first State to ratify an additional protocol, on 10 December 1997, and was the first State in which the IAEA exercised complementary access and managed access under an additional protocol. Australia has undergone three full cycles of evaluation under strengthened safeguards measures, enabling the Agency to conclude it was appropriate to commence implementation of integrated safeguards. In January 2001 Australia became the first State in which integrated safeguards are being applied. As such, Australia's experience will be of interest to other States as they consult with the IAEA on the modalities for the introduction of integrated safeguards in their jurisdictions. The purpose of the paper is to outline Australia's experience with strengthened safeguards and Australia's views on the implementation of integrated safeguards. Australia has five Material Balance Areas (MBAs), the principal one covering the 10 MWt research reactor at Lucas Heights and the associated inventory of fresh and irradiated HEU fuel. Under classical safeguards, generally Australia was subject to annual Physical Inventory Verifications (PIVs) for the four MBAs at Lucas Heights, plus quarterly interim inspections, making a total of four inspections a year (PIVs for the different MBAs were conducted concurrently with each other or with interim inspections in other MBAs), although there was a period when the fresh fuel inventory exceeded one SQ, requiring monthly inspections. Under strengthened safeguards, this pattern of four inspections a year was maintained, with the addition of complementary

  9. IAEA safeguards technical manual

    International Nuclear Information System (INIS)

    1982-03-01

    Part F of the Safeguards Technical Manual is being issued in three volumes. Volume 1 was published in 1977 and revised slightly in 1979. Volume 1 discusses basic probability concepts, statistical inference, models and measurement errors, estimation of measurement variances, and calibration. These topics of general interest in a number of application areas, are presented with examples drawn from nuclear materials safeguards. The final two chapters in Volume 1 deal with problem areas unique to safeguards: calculating the variance of MUF and of D respectively. Volume 2 continues where Volume 1 left off with a presentation of topics of specific interest to Agency safeguards. These topics include inspection planning from a design and effectiveness evaluation viewpoint, on-facility site inspection activities, variables data analysis as applied to inspection data, preparation of inspection reports with respect to statistical aspects of the inspection, and the distribution of inspection samples to more than one analytical laboratory. Volume 3 covers generally the same material as Volumes 1 and 2 but with much greater unity and cohesiveness. Further, the cook-book style of the previous two volumes has been replaced by one that makes use of equations and formulas as opposed to computational steps, and that also provides the bases for the statistical procedures discussed. Hopefully, this will help minimize the frequency of misapplications of the techniques

  10. Integrating virtual reality applications in nuclear safeguards

    International Nuclear Information System (INIS)

    Barletta, Michael; Crete, Jean-Maurice; Pickett, Susan

    2011-01-01

    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)

  11. Los Alamos safeguards program overview and NDA in safeguards

    International Nuclear Information System (INIS)

    Keepin, G.R.

    1988-01-01

    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

  12. Nuclear safeguards policy

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

    Claims have been made that Australia's nuclear safeguards policy, announced in 1977, has changed. However, examination of the texts of nuclear safeguards agreements negotiated by Australia shows that the policy has been implemented and adhered to. The purpose of these agreements is to obtain assurance that uranium exported is used exclusively for peaceful purposes. The questions of reprocessing, transfer to third countries and the application of IAEA safeguards are discussed

  13. New safeguards system and JNC's activities in the new safeguards system

    International Nuclear Information System (INIS)

    Iwanaga, Masayuki

    2000-01-01

    The Japan Nuclear Fuel Cycle Development Institute (JNC) has been developing the various area of the technology in the nuclear fuel cycle more than 30 years, as the leading organization. Standing on the accumulated experiences through those activities, JNC will construct the new fuel cycle concept based on the principle for safety, environment, economy and nonproliferation. In this process, evaluation of the specific nonproliferation features with the nuclear material control methods taking in to account of the safegurdability might have one of the major importance. On the other hand, recently, in addition to the conventional safeguards (INFCIRC153), an additional protocol (INFCIRC540) which defines the activities that complement the integrity of a member country's declaration has come into effect in several countries, including Japan. IAEA and other international organizations are now discussing the safeguards concept, which integrates the conventional as well as new safeguards measures. In JNC's efforts to construct the new fuel cycle concept, it is necessary to give sufficient consideration to reflect the integrated safeguards concept. In the process of implementing the concept of the new integrated safeguards system, we presume that changes will have to be made in the traditional approach, which mainly deals with nuclear material. It will become necessary to develop a concrete method and approach in order to analyze and evaluate information, and work will have to be undertaken to optimize such a method based on its effects and efficiency. JNC will make contributions to international society by making the best use of its experience and technological infrastructure to reflect further safeguards development program in JNC so that the new IAEA safeguards can be firmly established. Related to this point of view, the following two subjects is to be introduced on the whole; 1. JNC's experiences and expertise of the development of safeguards technology with the fuel

  14. Safeguard management for operation security in nuclear power plants (NPPs)

    International Nuclear Information System (INIS)

    Woo, Tae-Ho; Lee, Un-Chul

    2011-01-01

    Safeguard modeling is conducted for the successful operations in the nuclear power plants (NPPs). The characteristics of the secure operation in NPPs are investigated using the network effect method which is quantified by the Monte-Carlo algorithm. Fundamentally, it is impossible to predict the exact time of a terror incident. So, the random sampling for the event frequency is a reasonable method, including the characteristics of network effect method such as the zero-sum quantification. The performance of operation with safeguard is the major concern of this study. There are three kinds of considerations as the neutronics, thermo-hydraulics, and safeguard properties which are organized as an aspect of safeguard considerations. The result, therefore, can give the stability of the operations when the power is decided. The maximum value of secure operation is 12.0 in the third month and the minimum value is 1.0 in the 18th and 54th months, in a 10 years period. Thus, the stability of the secure power operation increases 12 times higher than the lowest value according to this study. This means that the secure operation is changeable in the designed NPPs and the dynamical situation of the secure operation can be shown to the operator.

  15. Nuclear safeguards in challenging times [Experts on nuclear safeguards and verification assess the global picture

    International Nuclear Information System (INIS)

    Park, W.S.; Hillerman, J.

    2007-01-01

    Meeting at the IAEA's International Safeguards Symposium in October 2006, more than 500 experts from 60-plus countries and organizations addressed current and future challenges related to safeguards concepts, approaches, technologies, and experience. Sessions addressed five main issues driving developments: Current challenges to the safeguards system; Further strengthening safeguards practices and approaches; Improving the collection and analysis of safeguards information; Advances in safeguards techniques and technology; and Future challenges. Every four to five years, the IAEA brings together safeguards experts from all over the world at international symposia. In October 2001, they met in the shadow of 9/11 and the symposium included a special session on the prevention of nuclear terrorism

  16. Safeguards systems analysis research and development and the practice of safeguards at DOE facilities

    International Nuclear Information System (INIS)

    Zack, N.R.; Thomas, K.E.; Markin, J.T.; Tape, J.W.

    1991-01-01

    Los Alamos Safeguards Systems Group personnel interact with Department of Energy (DOE) nuclear materials processing facilities in a number of ways. Among them are training courses, formal technical assistance such as developing information management or data analysis software, and informal ad hoc assistance especially in reviewing and commenting on existing facility safeguards technology and procedures. These activities are supported by the DOE Office of Safeguards and Security, DOE Operations Offices, and contractor organizations. Because of the relationships with the Operations Office and facility personnel, the Safeguards Systems Group research and development (R and D) staff have developed an understanding of the needs of the entire complex. Improved safeguards are needed in areas such as materials control activities, accountability procedures and techniques, systems analysis and evaluation methods, and material handling procedures. This paper surveys the generic needs for efficient and cost effective enhancements in safeguards technologies and procedures at DOE facilities, identifies areas where existing safeguards R and D products are being applied or could be applied, and sets a direction for future systems analysis R and D to address practical facility safeguards needs

  17. Safeguardability of advanced spent fuel conditioning process

    Energy Technology Data Exchange (ETDEWEB)

    Li, T. K. (Tien K.); Lee, S. Y. (Sang Yoon); Burr, Tom; Russo, P. A. (Phyllis A.); Menlove, Howard O.; Kim, H. D.; Ko, W. I. (Won Il); Park, S. W.; Park, H. S.

    2004-01-01

    The Advanced Spent Fuel Conditioning Process (ACP) is an electro-metallurgical treatment technique to convert oxide-type spent nuclear fuel into a metallic form. The Korea Atomic Energy Research Institute (KAERI) has been developing this technology since 1977 for the purpose of spent fuel management and is planning to perform a lab-scale demonstration in 2006. By using of this technology, a significant reduction of the volume and heat load of spent fuel is expected, which would lighten the burden of final disposal in terms of disposal size, safety and economics. In the framework of collaboration agreement to develop the safeguards system for the ACP, a joint study on the safeguardability of the ACP technology has been performed by the Los Alamos National Laboratory (LANL) and the KAERI since 2002. In this study, the safeguardability of the ACP technology was examined for the pilot-scale facility. The process and material flows were conceptually designed, and the uncertainties in material accounting were estimated with international target values.

  18. IAEA safeguards assessments

    International Nuclear Information System (INIS)

    Gruemm, H.; Parisick, R.; Pushkarjov, V.; Shea, T.; Brach, E.

    1981-01-01

    This paper describes the safeguards program administered by the IAEA, which must provide assurance to the international community that agency safeguards have the capacity to deter diversion, if contemplated, to detect diversion, if undertaken, and to provide assurance that no diversions have occurred when none are detected. This assurance to the international community is based upon the capability of the Agency's safeguards program to detect diversion and its complementary effect of deterrance

  19. The potential use of domestic safeguards interior monitors in International Safeguards

    International Nuclear Information System (INIS)

    Williams, J.D.; Dupree, S.A.; Sonnier, C.S.

    1998-01-01

    An important future element of International Safeguards instrumentation is expected to be the merging of containment/surveillance and nondestructive assay equipment with domestic physical protection equipment into integrated systems, coupled with remote monitoring. Instrumentation would include interior monitoring and assessment and entry/exit monitoring. Of particular importance is the application of interior monitors in spaces of declared inactivity; for example, in nuclear material storage locations that are entered infrequently. The use of modern interior monitors in International Safeguards offers potential for improving effectiveness and efficiency. Within the context of increased cooperation, one can readily envision increased interaction between International Safeguards and Domestic Safeguards, including increased joint use of State System of Accounting and Control data

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

    International Nuclear Information System (INIS)

    Bigliocca, C.

    1983-01-01

    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

  1. Experience of Brazilian safeguards analytical laboratory in DA analysis

    International Nuclear Information System (INIS)

    Bezerra, J.H.B.; Araujo, R.M.S.; Pereira, J.C.A.

    2001-01-01

    Full text: The Brazilian Safeguards Analytical Laboratory, inaugurated in September 1983, performs uranium analysis in samples of nuclear materials taken during national safeguards inspections as well as in samples taken during ABACC's inspections performed in Argentina. The Laboratory analyzes Intercomparison samples provided by IAEA, NBL, ABACC, CEN and EQRAIN. The method used to perform uranium analysis is the Davies and Gray/NBL. All the steps of the analytical procedures, such as chemical kinetics of the reactions and instrumental parameters, are rigorously controlled. An internal Quality Control of the measurements is made by means of analysis of Certified Reference Materials and the performance of the results meets the ESARDA's Target Values for Random and Systematic Components both in Intercomparison Samples and in samples taken during inspections. The typical precision, expressed as relative standard deviation, and accuracy obtained in a routine basis for nuclear grade materials is 0.1% and 0.14% respectively. The performance of the results obtained are comparable to the best international laboratories which perform uranium analysis in nuclear materials for safeguards purposes. (author)

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

    International Nuclear Information System (INIS)

    2014-01-01

    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.

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

    International Nuclear Information System (INIS)

    Brenner, L.M.; McDowell, S.C.T.

    1989-01-01

    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

  4. IAEA safeguards and detection of undeclared nuclear activities

    Energy Technology Data Exchange (ETDEWEB)

    Harry, R.J.S.

    1996-03-01

    Verfication of State declarations is an essential feature of IAEA safeguards. The issue of completeness of the declaration of all nuclear material, nuclear activities and nuclear facilities arises only in full scope safeguards, like those pursuant to NPT. Concentrating on the accountability aspect of nuclear material, the NPT safeguards system has achieved a high level of objective and quantified performance. Some of the basic ideas of the drafters of INFCIRC/153 (corrected) have been stalled. Non-proliferation concerns demand also for a detection probability for undeclared nuclear activities. Following the example of the Chemical Weapon Convention (CWC), advanced detection techniques are proposed, which go beyond the classical nuclear material accountability approach. Recent proposals for additional measures to strengthen IAEA safeguards conform to rules of NPT and related safeguards. Some proposals have been agreed generally, others can only be implemented on a voluntary basis between the State and the IAEA. The implementation will require additional resources and support for the IAEA. Great care is required to maintain the existing capability of the IAEA for a technically sound, independent, objective, and internationally acceptable judgement with available resources, and at the same time to change emphasis on certain elements of the existing safeguards system. (orig.).

  5. IAEA safeguards and detection of undeclared nuclear activities

    International Nuclear Information System (INIS)

    Harry, R.J.S.

    1996-03-01

    Verfication of State declarations is an essential feature of IAEA safeguards. The issue of completeness of the declaration of all nuclear material, nuclear activities and nuclear facilities arises only in full scope safeguards, like those pursuant to NPT. Concentrating on the accountability aspect of nuclear material, the NPT safeguards system has achieved a high level of objective and quantified performance. Some of the basic ideas of the drafters of INFCIRC/153 (corrected) have been stalled. Non-proliferation concerns demand also for a detection probability for undeclared nuclear activities. Following the example of the Chemical Weapon Convention (CWC), advanced detection techniques are proposed, which go beyond the classical nuclear material accountability approach. Recent proposals for additional measures to strengthen IAEA safeguards conform to rules of NPT and related safeguards. Some proposals have been agreed generally, others can only be implemented on a voluntary basis between the State and the IAEA. The implementation will require additional resources and support for the IAEA. Great care is required to maintain the existing capability of the IAEA for a technically sound, independent, objective, and internationally acceptable judgement with available resources, and at the same time to change emphasis on certain elements of the existing safeguards system. (orig.)

  6. Survey of nuclear safeguards in the European Community

    International Nuclear Information System (INIS)

    Gmelin, W.

    1992-01-01

    The control of the peaceful use of nuclear energy comprises activities related to nuclear safety, to the protection of persons and of the environment, to physical protection of the nuclear materials against theft or terrorism and to nuclear safeguards. Nuclear safeguards means the set of measures performed by the IAEA in the context of non-proliferation safeguards and, in the framework of the Euratom Treaty, those measures enabling the European Commission to satisfy itself that the nuclear material is not diverted from its intended and declared uses (particularly to unlawful non-peaceful applications) and that the obligations arising from International Agreements are complied with. This contribution to the International Conference on Peaceful Application of Nuclear Energy at Liege briefly reviews the history of nuclear safeguards in Europe since the early 1960ies. It also notes the practical aspects for, constraints and impacts to the nuclear operators imposed on them by the European law such as inspections, accountancy, reporting and describes the trend of the future development of the safeguards operation. The paper finally addresses non-proliferation issues and, notably, the relations between the IAEA and Euratom which in an exemplary way resulted in effective international safeguards and high non-proliferation credentials of the European Community. (author)

  7. Recent advances in safeguards operations

    International Nuclear Information System (INIS)

    Agu, B.; Iwamoto, H.

    1983-01-01

    The facilities and nuclear materials under IAEA safeguards have steadily increased in the past few years with consequent increases in the manpower and effort required for the implementation of effective international safeguards. To meet this challenge, various techniques and instruments have been developed with the assistance, support and cooperation of the Member States. Improved NDA equipment now permits accurate verification of plutonium and HEU bearing items; and optical and TV surveillance systems have improved remarkably. Experience in safeguarding nuclear facilities now includes fast-reactor fuel reprocessing and enrichment plants, even though the Hexapartite Safeguards Project is yet to define an agreed approach for safeguarding enrichment plants. The establishment of field offices now enables the IAEA to adequately implement safeguards at important facilities and also with more effective use of manpower. Closer cooperation with Member States via liaison or similar committees makes for effective safeguards implementation and the speedy solution of attendant problems. The technical support programmes from the Member States continue to provide the basis of the recent advances in safeguards techniques and instrumentation. (author)

  8. Implementation of remove monitoring in facilities under safeguards with unattended systems

    International Nuclear Information System (INIS)

    Beddingfield, David H.; Nordquist, Heather A.; Umebayaashi, Eiji

    2009-01-01

    Remote monitoring is being applied by the International Atomic Energy Agency (IAEA) at nuclear facilities around the world. At the Monju Reactor in Japan we have designed, developed and implemented a remote monitoring approach that can serve as a model for applying remote monitoring to facilities that are already under full-scope safeguards using unattended instrumentation. Remote monitoring implementations have historically relied upon the use of specialized data collection hardware and system design features that integrate remote monitoring into the safeguards data collection system. The integration of remote monitoring and unattended data collection increases the complexity of safeguards data collection systems. This increase in complexity necessarily produces a corresponding reduction of system reliability compared to less-complex unattended monitoring systems. At the Monju facility we have implemented a remote monitoring system that is decoupled from the activity of safeguards data collection. In the completed system the function of remote data transfer is separated from the function of safeguards data collection. As such, a failure of the remote monitoring function cannot produce an associated loss of safeguards data, as is possible with integrated remote-monitoring implementations. Currently, all safeguards data from this facility is available to the IAEA on a 24/7 basis. This facility employs five radiation-based unattended systems, video surveillance and numerous optical seal systems. The implementation of remote monitoring at this facility, while increasing the complexity of the safeguards system, is designed to avoid any corresponding reduction in reliability of the safeguards data collection systems by having decoupled these functions. This design and implementation can serve as a model for implementation of remote monitoring at nuclear facilities that currently employ unattended safeguards systems.

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

    International Nuclear Information System (INIS)

    Vidaurre-Henry, Jaime

    2001-01-01

    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)

  10. The Canadian safeguards program

    International Nuclear Information System (INIS)

    Zarecki, C.W.; Smith, R.M.

    1981-12-01

    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

  11. The application of probability methods for safeguards purposes

    International Nuclear Information System (INIS)

    Rumyantsev, A.N.

    1976-01-01

    The authors consider possible ways of applying probability methods to solve problems involved in accounting for nuclear materials. The increase in the flow of nuclear materials subject to IAEA safeguards makes it necessary to increase the accuracy of determination of the actual quantities of nuclear materials at all stages of their processing and use. It is proposed that the IAEA's automated system of accounting for nuclear materials, based on accounting information for each material balance zone and the results of random experimental checks performed by IAEA inspectors, be supplemented with mathematical models of the flow of nuclear materials in each balance zone based on the data supplied for each facility in the balance zone when it was placed under safeguards. The statistical error in determining the material balance and the material unaccounted for can be considerably reduced in this way even if the experimental control methods are retained. (author)

  12. IAEA safeguards glossary

    International Nuclear Information System (INIS)

    1980-01-01

    An unambiguous definition and rationalization of many of the terms for the purpose of IAEA safeguards are given, with a view to improving the common understanding of such terms within the international community. The glossary focuses only on safeguards meanings in general, and IAEA meanings in particular, of the terms discussed. Terms belong to the following problems: nuclear and non-nuclear material, nuclear equipment, design of the safeguards approach, nuclear material accountancy, physical standards, sampling, measurements, statistical concepts and others

  13. Implementation of the CNEN's safeguards laboratory

    International Nuclear Information System (INIS)

    Almeida, S.G. de

    1986-01-01

    The International Safeguards Agreements between Brazil and others countries has been concluded with the participation of the International Atomic Energy Agency (AIEA), and involve the Physical Protection and Control of Nuclear Material activities, which set up the National Safeguards System. The Safeguards Laboratory was constructed to the implementation and maintenance of this National Safeguards System, under responsability of CNEN's Safeguards Division, in order to carry out measurements of nuclear materials under safeguards. Technical requirements applied to the construction, setting up and operation of the laboratory are showed. The first results refer to the implementation of safeguards methods and techniques, as well as its participation within international scientific and technical co-operation programs in the safeguards area, through of them we wait its credencement by the AIEA as Regional Safeguards Laboratory for every countries of the Latin America. (Author) [pt

  14. Nuclear safeguards technology handbook

    International Nuclear Information System (INIS)

    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

  15. Safeguarding the functions and performance of instrumentation and control systems

    International Nuclear Information System (INIS)

    Koehler, M.; Schoerner, O.

    1996-01-01

    Based on an analysis of the existing nuclear power plant control technology, the necessity of providing in the medium-term advanced and future-oriented, digital control system, both for normal operation and for safety-relevant tasks of the reactor and safety control systems. Siemens KWU has been promoting the development, review and marketing of the digital instrumentation and control systems called TELEPERM XS and TELEPERM XP in addition to the measures taken for safeguarding the functions of existing, wired systems. The paper briefly explains the performance and advantages of digital systems and the progress in approval and pioneering of the TELEPERM XS safety control system. Many examples discussed show the diversity of applications of the systems both in new reactor plants and as retrofitting measures, for KWU power plants and those of other manufacturers. (orig.) [de

  16. 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)

  17. Psychology of nuclear safeguards. [Cannot guarantee preventing diversion, only deter

    Energy Technology Data Exchange (ETDEWEB)

    Parker, L

    1978-08-17

    There is an essential confusion in the way we look at safeguards. They cannot guarantee to prevent diversions: at best, they can deter. While successful acts of deterrence pass unnoticed, failures will be widely publicized. Therefore, we will judge safeguards systems not on a fair balance between their successes and failures, but exclusively on what we believe to be their failures. Effectively, we will be demanding an impossibly high standard of performance, and safeguards authorities will be tempted to conceal diversions rather than disappoint our expectations. Perhaps it is appropriate that safeguards are primarily psychological instruments: Parker argues that their essence is credibility, and that this does not necessarily depend on the hard reality of their performance. Brian Johnson claimed (New Scientist, vol 74, p 189) that safeguards have engendered a sense of security by linking the commitment of many states not to develop nuclear weapons, and that the Non-Proliferation Treaty has helped condition domestic political attitudes against starting up nuclear weapons programs. Perhaps the common view that safeguards are legal instruments has served the psychological purpose of supplying a language in which states with widely differing interests can explore the fundamental incompatibility between non-proliferation and the search for convenient energy sources. If this is true then it cannot be said that the NPT is a failure, merely that its success does not correspond to its apparent purposes.

  18. Safeguards Culture: lesson learned

    International Nuclear Information System (INIS)

    Frazar, S.; Mladineo, S.V.

    2010-01-01

    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.

  19. Minor isotope safeguards techniques (MIST): Analysis and visualization of gas centrifuge enrichment plant process data using the MSTAR model

    Science.gov (United States)

    Shephard, Adam M.; Thomas, Benjamin R.; Coble, Jamie B.; Wood, Houston G.

    2018-05-01

    This paper presents a development related to the use of minor isotope safeguards techniques (MIST) and the MSTAR cascade model as it relates to the application of international nuclear safeguards at gas centrifuge enrichment plants (GCEPs). The product of this paper is a derivation of the universal and dimensionless MSTAR cascade model. The new model can be used to calculate the minor uranium isotope concentrations in GCEP product and tails streams or to analyze, visualize, and interpret GCEP process data as part of MIST. Applications of the new model include the detection of undeclared feed and withdrawal streams at GCEPs when used in conjunction with UF6 sampling and/or other isotopic measurement techniques.

  20. Safeguard sleuths

    International Nuclear Information System (INIS)

    Lowry, D.

    1989-01-01

    A report of the conference of the European Safeguards Research and Development Association, which tries to prevent the diversion of nuclear materials to military uses is given. Some of the problems encountered by safeguards inspectors are mentioned, such as being able to follow the material through the maze of piping in a reprocessing plant, the linguistic difficulties if the inspector does not speak the operator's language, the difference between precision and accuracy and the necessity of human inspection, containment and surveillance systems. Unexplained outages at a reprocessing plant are always treated as suspicious, as are power failures which prevent normal surveillance. The UK practice of allocating civil fuel temporarily to military use at Harwell also makes safeguard policing more difficult. (UK)

  1. Computer-based safeguards information and accounting system

    International Nuclear Information System (INIS)

    1977-01-01

    seminars for States' personnel. For the safeguards trilateral agreements under INFCIRC/66, the Agency operates a semi-automated system to handle data arising from the joint notification, inventory reports and advance notifications. Although a considerable amount of nuclear material is safeguarded under these agreements, the reporting of information is less standardized and less timely than under NPT agreements. The Department of Safeguards is working with Member States toward the use of a new subsidiary arrangement model containing more standardized reporting procedures. The IAEA is also sponsoring workshops and seminars to train the States' personnel in reporting procedures and to explain and correct existing problems of reporting. (author)

  2. Safeguards Envelope Progress FY10

    International Nuclear Information System (INIS)

    Metcalf, Richard

    2010-01-01

    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.

  3. IAEA symposium on international safeguards

    International Nuclear Information System (INIS)

    1999-01-01

    The eighth IAEA Symposium on International Safeguards was organized by the IAEA in cooperation with the Institute of Nuclear Materials Management and the European Safeguards Research and Development Association. It was attended by over 350 specialists and policy makers in the field of nuclear safeguards and verification from more than 50 countries and organizations. The purpose of the Symposium was to foster a broad exchange of information on concepts and technologies related to important developments in the areas of international safeguards and security. For the first time in the history of the symposia, the IAEA is issuing proceedings free of charge to participants on CD-ROM. The twenty-two plenary, technical, and poster sessions featured topics related to technological and policy aspects from national, regional and global perspectives. The theme of the Symposium: Four Decades of Development - Safeguarding into the New Millennium set the stage for the commemoration of a number of significant events in the annals of safeguards. 1997 marked the Fortieth Anniversary of the IAEA, the Thirtieth Anniversary of the Tlatelolco Treaty, and the Twentieth Anniversary of the Department of Safeguards Member State Support Programmes. There were special events and noted presentations featuring these anniversaries and giving the participants an informative retrospective view of safeguards development over the past four decades. The proceedings of this symposium provide the international community with a comprehensive view of where nuclear safeguards and verification stood in 1997 in terms of the growing demands and expectations. The Symposium offered thoughtful perspectives on where safeguards are headed within the broader context of verification issues. As the world of international nuclear verification looks towards the next millennium, the implementation of the expanding and strengthened safeguards system presents formidable challenges

  4. DOE assessment guide for safeguards and security

    International Nuclear Information System (INIS)

    Bennett, C.A.; Christorpherson, W.E.; Clark, R.J.; Martin, F.; Hodges, Jr.

    1978-04-01

    DOE operations are periodically assessed to assure that special nuclear material, restricted data, and other classified information and DOE facilities are executed toward continuing the effectiveness of the International Atomic Energy Agency safeguards. A guide to describe the philosophy and mechanisms through which these assessments are conducted is presented. The assessment program is concerned with all contractor, field office, and Headquarters activities which are designed to assure that safeguards and security objectives are reached by contractors at DOE facilities and operations. The guide takes into account the interlocking relationship between many of the elements of an effective safeguards and security program. Personnel clearance programs are a part of protecting classified information as well as nuclear materials. Barriers that prevent or limit access may contribute to preventing theft of government property as well as protecting against sabotage. Procedures for control and surveillance need to be integrated with both information systems and procedures for mass balance accounting. Wherever possible, assessment procedures have been designed to perform integrated inspection, evaluation, and follow-up for the safeguards and security program

  5. Safeguards Evaluation Method for evaluating vulnerability to insider threats

    International Nuclear Information System (INIS)

    Al-Ayat, R.A.; Judd, B.R.; Renis, T.A.

    1986-01-01

    As protection of DOE facilities against outsiders increases to acceptable levels, attention is shifting toward achieving comparable protection against insiders. Since threats and protection measures for insiders are substantially different from those for outsiders, new perspectives and approaches are needed. One such approach is the Safeguards Evaluation Method. This method helps in assessing safeguards vulnerabilities to theft or diversion of special nuclear meterial (SNM) by insiders. The Safeguards Evaluation Method-Insider Threat is a simple model that can be used by safeguards and security planners to evaluate safeguards and proposed upgrades at their own facilities. The method is used to evaluate the effectiveness of safeguards in both timely detection (in time to prevent theft) and late detection (after-the-fact). The method considers the various types of potential insider adversaries working alone or in collusion with other insiders. The approach can be used for a wide variety of facilities with various quantities and forms of SNM. An Evaluation Workbook provides documentation of the baseline assessment; this simplifies subsequent on-site appraisals. Quantitative evaluation is facilitated by an accompanying computer program. The method significantly increases an evaluation team's on-site analytical capabilities, thereby producing a more thorough and accurate safeguards evaluation

  6. 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

  7. Technology development for safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ho Dong; Kang, H. Y.; Song, D. Y. [and others

    2005-04-01

    The objective of this project are to establish the safeguards technology of the nuclear proliferation resistance to the facilities which handle with high radioactivity nuclear materials like the spent fuel, to provide the foundation of the technical independency for the establishment of the effective management of domestic spent fuels, and to construct the base of the early introduction of the key technology relating to the back-end nuclear fuel cycle through the development of the safeguards technology of the DFDF of the nuclear non-proliferation. The essential safeguards technologies of the facility such as the measurement and account of nuclear materials and the C/S technology were carried out in this stage (2002-2004). The principal results of this research are the development of error reduction technology of the NDA equipment and a new NDA system for the holdup measurement of process materials, the development of the intelligent surveillance system based on the COM, the evaluation of the safeguardability of the Pyroprocessing facility which is the core process of the nuclear fuel cycle, the derivation of the research and development items which are necessary to satisfy the safeguards criteria of IAEA, and the presentation of the direction of the technology development relating to the future safeguards of Korea. This project is the representative research project in the field of the Korea's safeguards. The safeguards technology and equipment developed while accomplishing this project can be applied to other nuclear fuel cycle facilities as well as DFDF and will be contributed to increase the international confidence in the development of the nuclear fuel cycle facility of Korea and its nuclear transparency.

  8. DOE/ABACC safeguards cooperation

    International Nuclear Information System (INIS)

    Whitaker, J.M.; Toth, P.; Rubio, J.

    1995-01-01

    In 1994, the US Department of Energy (DOE) and the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC) signed a safeguards cooperation agreement. The agreement provides for cooperation in the areas of nuclear material control, accountancy, verification, and advanced containment and surveillance technologies for international safeguards applications. ABACC is an international safeguards organization responsible for verifying the commitments of a 1991 bilateral agreement between Argentina and Brazil in which both countries agreed to submit all nuclear material in all nuclear activities to a Common System of Accounting and Control of Nuclear Materials (SCCC). DOE provides critical assistance (including equipment and training) through the Office of Nonproliferation and National Security to countries and international organizations to enhance their capabilities to control and verify nuclear material inventories. Specific activities initiated under the safeguards agreement include: (1) active US participation in ABACC's safeguards training courses, (2) joint development of specialized measurement training workshops, (3) characterization of laboratory standards, and (4) development and application of an extensive analytical laboratory comparison program. The results realized from these initial activities have been mutually beneficial in regard to strengthening the application of international safeguards in Argentina and Brazil

  9. 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.

  10. IAEA Safeguards: Cost/benefit analysis of commercial satellite imagery

    International Nuclear Information System (INIS)

    Andersson, Christer

    1999-03-01

    A major milestone in the efforts to strengthen the Safeguards System was reached in May 1997 when the Board of Governors approved a 'Model Protocol Additional to Safeguards Agreements'. The Protocol provides the legal basis necessary to enhance the Agency's ability to detect undeclared nuclear material and activities by using information available from open sources to complement the declarations made by Member States. Commercially available high-resolution satellite data has emerged as one potential complementary open information source to support the traditional and extended Safeguard activities of IAEA. This document constitutes a first report from SSC Satellitbild giving the Agency tentative and initial estimates of the potential cost and time-savings possible with the new proposed technology. The initial cost/benefit simulation will be further finalised in the following 'Implementation Blueprint' study. The general foundation and starting point for the cost/benefit calculation is to simulate a new efficient and relatively small 'imagery unit' within the IAEA, capable of performing advanced image processing as a tool for various safeguards tasks. The image processing capacity is suggested to be task- and interpretation-oriented. The study was performed over a period of 1,5 weeks in late 1998, and is based upon interviews of IAEA staff, reviews of existing IAEA documentation as well as from SSC Satellitbild's long-standing experience of satellite imagery and field missions. The cost/benefit analysis is based on a spreadsheet simulation of five potential applications of commercial satellite imagery: Reference information; Confirmation of Agency acquired and Member State supplied data; Change detection and on-going monitoring; Assessing open source information available to the Agency; Detecting undeclared activities and undeclared sites. The study confirms that the proposed concept of a relatively small 'imagery unit' using high-resolution data will be a sound and

  11. An overview of artificial intelligence applications to safeguards

    International Nuclear Information System (INIS)

    Johnson, C.E.

    1987-01-01

    The rapidly growing discipline of artificial intelligence (AI) has delivered a number of expert systems that aid analyses of processes and procedures by emulating the analysis and decisions of experts. Expert systems have not reached the point of replacing experts, but can provide assistance in their absence. In narrow domains, expert systems can relieve the expert of less demanding analyses and decisions, freeing him/her for more important tasks. Safeguards experts are in great demand, and the decision processes they perform are not always well-defined. The general area of safeguards analysis is representative of the type of activity that benefits from the assistance provided by AI techniques. The American Nuclear Society is holding a topical meeting, Artificial Intelligence and Other Innovative Computer Applications in the Nuclear Industry, on August 31-September 2, 1987. The technical papers cover a number of applications of potential benefit to safeguards and the safeguards interface with facility operations. This paper is a technical review of papers presented at the topical meeting

  12. Structure of safeguards systems

    International Nuclear Information System (INIS)

    Shipley, J.P.

    1978-06-01

    An effective safeguards system for domestic nuclear fuel cycle facilities consists of several important subsystems that must coordinate their functions with plant management and process control. The safeguards system must not unnecessarily disrupt plant operations, compromise safety requirements, or infringe on employee working conditions. This report describes concepts, which have been developed with the cooperation of the nuclear industry and the safeguards community, for achieving these objectives

  13. Safeguards as catastrophic risk management: insights and projections

    International Nuclear Information System (INIS)

    Leffer, T.N.

    2013-01-01

    The system of international agreements designed to prevent the use of nuclear weapons and to control the spread of nuclear weapons, materials and technologies (collectively referred to as the nuclear arms control and nonproliferation regimes) is posited as humanity.s first attempt to mitigate a man-made global catastrophic risk. By extrapolating general principles of government response to risk from the arms control and nonproliferation regimes, a model of international regime building for catastrophic risk mitigation is constructed. This model provides the context for an examination of the system of safeguards implemented by the International Atomic Energy Agency (IAEA), which serves as the nuclear nonproliferation regime.s verification and enforcement mechanism and thereby constitutes the regime's most completely developed discrete mechanism for risk mitigation (a 'system within a system'). An assessment of the history, evolution and effectiveness of the IAEA safeguards system in the context of the regimes-as-risk-mitigation model reveals some general principles for risk-mitigation regimes which are then applied to the safeguards system to identify ways in which it may be strengthened. Finally, the IAEA safeguards system is posited as the prototype verification/enforcement mechanism for future risk mitigation regimes that governments will be compelled to create in the face of new global catastrophic risks that technological advance will inevitably create. (author)

  14. Novel technologies for safeguards

    International Nuclear Information System (INIS)

    Annese, C.; Monteith, A.; Whichello, J.

    2009-01-01

    Full-text: The International Atomic Energy Agency (IAEA) Novel Technologies Project is providing access to a wider range of methods and instruments, as well as establishing a systematic mechanism to analyse gaps in the inspectorate's technical support capabilities. The project also targets emerging and future inspectorate needs in the areas of verification and the detection of undeclared nuclear activities, materials, and facilities, providing an effective pathway to technologies in support of safeguards implementation. The identification of safeguards-useful nuclear fuel cycle (NFC) indicators and signatures (I and S) is a fundamental sub-task within the Project. It interfaces with other IAEA efforts currently underway to develop future safeguards approaches through undertaking an in-depth review of NFC processes. Primarily, the sub-task aims to identify unique and safeguards-useful 'indicators', which identify the presence of a particular process, and 'signatures', which emanate from that process when it is in operation. The matching of safeguards needs to detection tool capabilities facilitates the identification of gaps where no current method or instrument exists. The Project has already identified several promising technologies based on atmospheric gas sampling and analysis, laser spectrometry and optically stimulated luminescence. Instruments based on these technologies are presently being developed through support programme tasks with Member States. This paper discusses the IAEA's project, Novel Technologies for the Detection of Undeclared Nuclear Activities, Materials and Facilities and its goal to develop improved methods and instruments. The paper also describes the method that has been devised within the Project to identify safeguards-useful NFC I and S and to determine how the sub-task interfaces with other IAEA efforts to establish emerging safeguards approaches. As with all safeguards-targeted research and development (R and D), the IAEA depends

  15. The Agency's Safeguards System (1965)

    International Nuclear Information System (INIS)

    1965-01-01

    On 28 September 1965 the Board of Governors approved the Agency's revised safeguards system which is set forth in this document for the information of all Members. For ease of reference the revised system may be cited as 'The Agency's Safeguards System (1965)' to distinguish it from the original system - 'The Agency's Safeguards System (1961)'- and from the original system as extended to large reactor facilities - 'The Agency's Safeguards System (1961, as Extended in 1964)'

  16. 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 it is difficult to detect diversion or undeclared irradiation. In addition, infrastructure associated with research reactors could pose a safeguards challenge. To strengthen the effectiveness of safeguards at the State level, this paper advocates that the IAEA consider ways to focus additional attention and broaden its safeguards toolbox for research reactors. This increase in focus on the research reactors could begin with the recognition that the research reactor (of any size) could be a common path element on a large number of technically plausible pathways that must be considered when performing acquisition pathway analysis (APA) for developing a State Level Approach (SLA) and Annual Implementation Plan (AIP). To

  17. Implementation of a Strengthened International Safeguards System ABBAC 15 years

    International Nuclear Information System (INIS)

    Vicens, Hugo; Maceiras, Elena; Dominguez, Cristina A.

    2008-01-01

    The purpose of the paper is to explain how the system of a regional safeguard has been operating and developing in the framework of the Brazilian Argentine Agency for Accounting and Control of Nuclear Materials (ABACC), and how the international recommendation of radiological protection must be taken into account in the safeguards implementation and its impact in the international context. The ABACC has been a dynamic system, which contributes worldwide in the application of the regional and international safeguard. In 2006, the ABACC celebrated its 15th anniversary. The ABBAC was created in 1991 in the framework of a Bilateral Agreement for the Exclusively Peaceful use of Nuclear Energy, the ABBAC was created in order to apply the aforementioned system called 'Common System for Accounting and Control of Nuclear Materials' (SCCC). During this time, the ABBAC has grown in its implementation and has become a model in the application of regional safeguards that is recognized internationally. The ABBAC was the pillar to signed an Agreement between Argentina, Brazil, the ABBAC and the International Atomic Energy Agency, called 'Quadripartite Agreement', committed themselves to accept the application of safeguards to all nuclear materials in all the nuclear activities performed in both countries. The ABACC and the relevant implementing and supplementary agreements, set forth the conditions for the peaceful use of nuclear energy, the exchange of technical staff, the transfer of knowledge and international cooperation in a strong commitment to non-proliferation of nuclear weapons. This introduction provides an overview of political, legal and technical aspects implemented in the ABACC, which will be developed later in the paper. (author)

  18. System aspects on safeguards for the back-end of the Swedish nuclear fuel cycle

    International Nuclear Information System (INIS)

    Fritzell, Anni

    2008-03-01

    This thesis has investigated system aspects of safeguarding the back-end of the Swedish nuclear fuel cycle. These aspects include the important notion of continuity of knowledge, the philosophy of verifying measurements and the need to consider the safeguards system as a whole when expanding it to include the encapsulation facility and the geological repository. The research has been analytical in method both in the identification of concrete challenges for the safeguards community in Paper 1, and in the diversion path analysis performed in Paper 2. This method of work is beneficial for example when abstract notions are treated. However, as a suggestion for further work along these lines, a formal systems analysis would be advantageous, and may even reveal properties of the safeguards system that the human mind so far has been to narrow to consider. A systems analysis could be used to model a proposed safeguards approach with the purpose of finding vulnerabilities in its detection probabilities. From the results, capabilities needed to overcome these vulnerabilities could be deduced, thereby formulating formal boundary conditions. These could include: The necessary partial defect level for the NDA measurement; The level of redundancy required in the C/S system to minimize the risk of inconclusive results due to equipment failure; and, Requirements on the capabilities of seismic methods, etc. The field of vulnerability assessment as a tool for systems analysis should be of interest for the safeguards community, as a formal approach could give a new dimension to the credibility of safeguards systems

  19. System aspects on safeguards for the back-end of the Swedish nuclear fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Fritzell, Anni (Dept. of Physics and Astronomy, Uppsala Univ., Uppsala (Sweden))

    2008-03-15

    This thesis has investigated system aspects of safeguarding the back-end of the Swedish nuclear fuel cycle. These aspects include the important notion of continuity of knowledge, the philosophy of verifying measurements and the need to consider the safeguards system as a whole when expanding it to include the encapsulation facility and the geological repository. The research has been analytical in method both in the identification of concrete challenges for the safeguards community in Paper 1, and in the diversion path analysis performed in Paper 2. This method of work is beneficial for example when abstract notions are treated. However, as a suggestion for further work along these lines, a formal systems analysis would be advantageous, and may even reveal properties of the safeguards system that the human mind so far has been to narrow to consider. A systems analysis could be used to model a proposed safeguards approach with the purpose of finding vulnerabilities in its detection probabilities. From the results, capabilities needed to overcome these vulnerabilities could be deduced, thereby formulating formal boundary conditions. These could include: The necessary partial defect level for the NDA measurement; The level of redundancy required in the C/S system to minimize the risk of inconclusive results due to equipment failure; and, Requirements on the capabilities of seismic methods, etc. The field of vulnerability assessment as a tool for systems analysis should be of interest for the safeguards community, as a formal approach could give a new dimension to the credibility of safeguards systems

  20. The SSAC in international safeguards and non-proliferation aspects

    International Nuclear Information System (INIS)

    Bett, F.L.; Humphreys, J.J.

    1989-01-01

    The history of international efforts against horizontal proliferation, including the Baruch Plan, bilateral safeguards agreement, IAEA safeguards, the Nuclear Non-Proliferation Treaty, the Zangger Committee, the Nuclear Supplier Group guidelines and the Physical Protection Convention, is reviewed. The role of IAEA NPT safeguards in verifying nondiversion and ensuring no misuse of supplied nuclear items is discussed. The vital importance of successful performance of this role to peaceful nuclear commerce is stressed. The application of NPT safeguards by the IAEA is described, particularly the IAEA's requirement that a State System of Accounting for and Control of Nuclear Material be established. Such a State System has two different but complementary areas of responsibility - ensuring that the use of nuclear material is controlled effectively and can be readily accounted for (this includes the area of physical protection), and providing accounts of nuclear material to responsible bodies such as the State's government and equally importantly to the IAEA for safeguards purpose, as the IAEA bases its conclusions about diversion on its verification of the data provided by the State System

  1. Safeguards-by-Design: An Element of 3S Integration

    International Nuclear Information System (INIS)

    Bean, R.S.; Bjornard, T.A.; Hebdich, D.J.

    2009-01-01

    In 2008, the '20/20 Vision for the Future' background report by the IAEA Director General identified the possibility of integrating certain activities related to safeguards, safety, and security. Later in the year, the independent Commission report prepared at the request of the IAEA Director General noted that the Agency's's roles in nuclear safeguards, safety, and security (3S) complement and can mutually reinforce each other. Safeguards-by-design (SBD) is a practical measure that strengthens 3S integration, especially for the stage of nuclear facility design and construction, but also with ramifications for other stages of the facility life-cycle. This paper describes the SBD concept, with examples for diverse regulatory environments, being developed in the U.S under the U.S. Department of Energy (DOE) Next Generation Safeguards Initiative and the Advanced Fuel Cycle Initiative. This is compared with related international SBD work performed in the recent IAEA workshop on 'Facility Design and Plant Operation Features that Facilitate the Implementation of IAEA Safeguards'. Potential future directions for further development of SBD and its integration within 3S are identified.

  2. Risk-informed approach for safety, safeguards, and security (3S) by design

    International Nuclear Information System (INIS)

    Suzuki, Mitsutoshi; Burr, Tom; Howell, John

    2011-01-01

    Over several decades the nuclear energy society worldwide has developed safety assessment methodology based on probabilistic risk analysis for incorporating its benefit into design and accident prevention for nuclear reactors. Although safeguards and security communities have different histories and technical aspects compared to safety, risk assessment as a supplement to their current requirements could be developed to promote synergism between Safety, Safeguards, and Security (3S) and to install effective countermeasures in the design of complex nuclear fuel cycle facilities. Since the 3S initiative was raised by G8 countries at Hokkaido Toyako-Summit in 2008, one approach to developing synergism in a 3S By Design (3SBD) process has been the application of risk-oriented assessment methodology. In the existing regulations of safeguards and security, a risk notion has already been considered for inherent threat and hazard recognition. To integrate existing metrics into a risk-oriented approach, several mathematical methods have already been surveyed, with attention to the scarcity of intentional acts in the case of safeguards and the sparseness of actual event data. A two-dimensional probability distribution composed of measurement error and incidence probabilities has been proposed to formalize inherent difficulties in the International Atomic Energy Agency (IAEA) safeguards criteria. In particular, the incidence probability that is difficult to estimate has been explained using a Markov model and game theory. In this work, a feasibility study of 3SBD is performed for an aqueous reprocessing process, and synergetic countermeasures are presented for preliminary demonstration of 3SBD. Although differences and conflicts between individual 'S' communities exist, the integrated approach would be valuable for optimization and balance between the 3S design features as well as for effective and efficient implementation under existing regulation frameworks. In addition

  3. Safeguards for geological repositories

    International Nuclear Information System (INIS)

    Fattah, A.

    2000-01-01

    Direct disposal of spent nuclear fuel in geological repositories is a recognised option for closing nuclear fuel cycles. Geological repositories are at present in stages of development in a number of countries and are expected to be built and operated early next century. A State usually has an obligation to safely store any nuclear material, which is considered unsuitable to re-enter the nuclear fuel cycle, isolated from the biosphere. In conjunction with this, physical protection has to be accounted for to prevent inadvertent access to such material. In addition to these two criteria - which are fully under the State's jurisdiction - a third criterion reflecting international non-proliferation commitments needs to be addressed. Under comprehensive safeguards agreements a State concedes verification of nuclear material for safeguards purposes to the IAEA. The Agency can thus provide assurance to the international community that such nuclear material has been used for peaceful purposes only as declared by the State. It must be emphasised that all three criteria mentioned constitute a 'unit'. None can be sacrificed for the sake of the other, but compromises may have to be sought in order to make their combination as effective as possible. Based on comprehensive safeguards agreements signed and ratified by the State, safeguards can be terminated only when the material has been consumed or diluted in such a way that it can no longer be utilised for any nuclear activities or has become practicably irrecoverable. As such safeguards for nuclear material in geological repositories have to be continued even after the repository has been back-filled and sealed. The effective application of safeguards must assure continuity-of-knowledge that the nuclear material in the repository has not been diverted for an unknown purpose. The nuclear material disposed in a geological repository may eventually have a higher and long term proliferation risk because the inventory is

  4. Strengthening regional safeguards

    International Nuclear Information System (INIS)

    Palhares, L.; Almeida, G.; Mafra, O.

    1996-01-01

    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

  5. Safeguards Implementation Practices Guide on Facilitating IAEA Verification Activities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-12-15

    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

  6. Safeguards Implementation Practices Guide on Facilitating IAEA Verification Activities

    International Nuclear Information System (INIS)

    2014-01-01

    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

  7. Nuclear safeguards research and development

    Science.gov (United States)

    Henry, C. N.

    1981-11-01

    The status of a nuclear safeguard research and development program is presented. Topics include nondestructive assay technology development and applications, international safeguards, training courses, technology transfer, analytical chemistry methods for fissionable materials safeguards, the Department of Energy Computer Security Technical Center, and operational security.

  8. Implementation of Safeguards in Thailand

    International Nuclear Information System (INIS)

    Rueanngoen, A.; Changkrueng, K.; Srijittawa, L.; Mungpayaban, H.; Wititteeranon, A.

    2015-01-01

    Thailand is a non-nuclear weapon state. The non-nuclear activities are mainly medical, agricultural, and industrial. Therefore, Thailand ratified the Nuclear Non-Proliferation Treaty (NPT) since 1972 and has been entry into force of the Comprehensive Safeguards Agreement (INFCIRC 241) since 1974. Based on the INFCIRC 153, Thailand established a system of accounting for and control of all nuclear material subject to safeguards under the Agreement. In order to ensure the peaceful use of nuclear in Thailand the Nuclear-Non- Proliferation Center of Office of Atoms for Peace (NPC, OAP) was established to act as State level Safeguards. NPC is responsible for keeping records and providing information under requirement of Comprehensive Safeguards Agreement. In addition, the strengthening of cooperation and good coordination between Thailand and IAEA are indeed important and necessary to implementation safeguards in country. Based on the report of IAEA safeguards statement, there is no indication of the diversion of nuclear materials or misuse of the facility or the items in Thailand. Up to present, nuclear activities in Thailand are peaceful without diversion of using. This paper reviews the current status of the implementation Safeguards in Thailand. (author)

  9. Tokai advanced safeguards technology exercise task T-F: study of selected capabilities needed to apply DYMAC principles to safeguarding the Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Lowry, L.L.; Augustson, R.H.

    1979-10-01

    Selected technical capabilities needed to apply the DYMAC principles to safeguarding the Tokai reproprocessing plant are presented. The measurements needed to close the mass balance around the process line and the analysis methods for assessing the results were investigated. Process conditions at the Tokai plant were used when numerical values were needed to assist the analyis. A rationale is presented for the selection of instruments (x-ray fluorescence spectrometers, x-ray densitometers, and gamma-ray spectrometers) best suited to establishing plutonium concentrations and inventories in the feed tanks. The current state of the art in estimating inventory in contactors is reviewed and profitable directions for further work are recommended. A generalized performance surface has been developed that can measure the diversion sensitivity of the safeguard system when the instrument performance levels, the number of measurements made, and the false alarm probability are specified. An analysis of its application to the Tokai plant is given. Finally, a conceptual approach to the problem of IAEA safeguards verification is discussed. It appears possible that, in the process of verifying, the full power of the plant operator's safeguard system can be brought to the service of the IAEA

  10. IAEA safeguard system

    International Nuclear Information System (INIS)

    Pontes, B.C.

    1987-01-01

    The intents of IAEA safeguards, analysing into the IAEA statutes, are presented. The different types of safeguard agreements; the measurements of accounting, containment and caution used by the operator and; the information to be provided and the verification to be developed by IAEA are described. (M.C.K.) [pt

  11. Modeling and simulation in the design and evaluation of conceptual safeguards systems

    International Nuclear Information System (INIS)

    Cobb, D.D.; Smith, D.B.

    1977-01-01

    Recent work in modeling nuclear fuel-cycle processes and the materials measurement and accountability portion of integrated safeguards systems is summarized. Process variability, especially in the levels of in-process holdup and in scrap and waste sidestreams, impacts significantly on the design of dynamic materials accounting and control systems. In the absence of operating data from modern facilities, detailed dynamic models of process operation are required in order to evaluate systems design concepts. Numerical data are presented from the simulated operation of major portions of spent fuel reprocessing, plutonium nitrate-to-oxide conversion, and mixed-oxide fuel-fabrication processes

  12. Current technical issues in international safeguards

    International Nuclear Information System (INIS)

    Bennett, C.A.

    1977-01-01

    Safeguards systems, and the associated need for technical and systems development, reflect changing conditions and concerns associated with the nuclear fuel cycle and the safety and security of nuclear materials and facilities. In particular, the implementation of international safeguards has led to the recognition of certain technical issues, both old and new, which are in need of resolution. These are: 1. The grading of nuclear materials and facilities with respect to their relative safeguards significance. 2. The extension and upgrading of safeguards techniques to maintain adequate protection in view of constantly increasing amounts of material to be safeguarded. 3. The balance between safeguards mechanisms based on physical protection and material accounting, and the role of surveillance and containment in each case. 4. The role of information systems as a basis for both analytical feedback and the determination of the factors affecting system effectiveness and their interrelationship. 5. A determination of the degree to which the overall technical effectiveness of international inspection activities can be quantified. Each of these technical issues must be considered in light of the specific objectives of international safeguards, which differ from domestic safeguards in terms of the level of the threat, the safeguards mechanisms available, and the diversion strategies assumed. Their resolution in this international context is essential if the effectiveness and viability of international safeguards are to be maintained

  13. Safeguarding the Plutonium Fuel Cycle

    International Nuclear Information System (INIS)

    Johnson, S.J.; Lockwood, D.

    2013-01-01

    In developing a Safeguards Approach for a plutonium process facility, two general diversion and misuse scenarios must be addressed: 1) Unreported batches of undeclared nuclear material being processed through the plant and bypassing the accountancy measurement points, and 2) The operator removing plutonium at a rate that cannot be detected with confidence due to measurement uncertainties. This paper will look at the implementation of international safeguards at plutonium fuel cycle facilities in light of past lessons learned and current safeguards approaches. It will then discuss technical areas which are currently being addressed as future tools to improve on the efficiency of safeguards implementation, while maintaining its effectiveness. The discussion of new improvements will include: safeguards by design (SBD), process monitoring (PM), measurement and monitoring equipment, and data management. The paper is illustrated with the implementation of international safeguards at the Rokkasho Reprocessing Plant in Japan and its accountancy structure is detailed. The paper is followed by the slides of the presentation

  14. Safeguards agreements - Their legal and conceptual basis

    International Nuclear Information System (INIS)

    Sanders, B.; Rainer, R.H.

    1977-01-01

    The application of Agency safeguards requires treaty arrangements (Safeguards Agreements) between the State or States concerned and the Agency. The authority for the Agency to conclude such agreements and to implement them is provided for in the Agency's Statute. On the basis of the statutory provisions safeguards principles and procedures have been elaborated. These have been laid down in: The Agency's Safeguards System 1965, extended in 1966 and 1968; and the basis for negotiating safeguards agreements with NNWS pursuant to NPT. The verification of the undertaking by the State concerned not to use items subject to safeguards for purposes contrary to the terms of the agreement is ensured through the application of various safeguards measures. Containment and surveillance measures are expected to play an increasingly important role. One of the specific features of NPT Safeguards Agreements is the establishment of national systems of accounting and control of nuclear material. The majority of the agreements concluded under the non-NPT safeguards agreements implement obligations undertaken under co-operation agreements between States for peaceful uses of nuclear energy. These agreements naturally reflect approaches adopted by the parties, in particular regarding the circumstances under which safeguards should be applied. Thus, the concepts used in the non-NPT safeguards agreements and the Safeguards System document, which is incorporated in these agreements by reference, are in continuous evolution. The Agency's Safeguards System document (INFCIRC/66/Rev.2) continues to be supplemented in practical application and through explicit decision by the Board. The non-NPT safeguards agreements contain, besides technical safeguards provisions from this document, and further provision for notification, inventories and financial matters, legal and political provisions such as sanctions in the case of non-compliance, and privileges and immunities. The paper discusses the

  15. IAEA safeguards for the 21st century

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-07-01

    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 ofregional non-proliferation arrangements in international nuclear verification; promotion of transparency through Korean experience; and the future prospects of safeguards.

  16. Status and Prospect of Safeguards By Design for Pyroprocessing Facility

    International Nuclear Information System (INIS)

    Kim, Ho-Dong; Shin, H.S.; Ahn, S.K.

    2010-01-01

    The concept of Safeguards-By-Design (SBD), which is proposed and developed by the United States and the IAEA, is now widely acknowledged as a fundamental consideration for the effective and efficient implementation of safeguards. The application of a SBD concept is of importance especially for developmental nuclear facilities which have new technological features and relevant challenges to their safeguards approach. At this point of time, the examination of the applicability of SBD on a pyroprocessing facility, which has been being developed in the Republic of Korea (ROK), would be meaningful. The ROK developed a safeguards system with the concept of SBD for Advanced spent fuel Conditioning Process Facility (ACPF) and DUPIC Fuel Development Facility (DFDF) before the SBD concept was formally suggested. Currently. The PRIDE (PyRoprocess Integrated Inactive Demonstration) facility for the demonstration of pyroprocess using 10 ton of non-radioactive nuclear materials per year is being constructed in the ROK. The safeguards system for the facility has been designed in cooperation with a facility designer from the design phase, and the safeguards system would be established according to the future construction schedule. In preparing the design of Engineering Scale Pyroprocess Facility (ESPF), which will use spent fuels in an engineering scale and be constructed in 2016, a research on the safeguards system for this facility is also being conducted. In this connection, a project to support for development of safeguards approach for a reference pyroprocessing facility has been carried out by KAERI in cooperation with KINAC and the IAEA through an IAEA Member State Support Program (MSSP). When this MSSP project is finished in August, 2011, a safeguards system model and safeguards approach for a reference pyroprocessing facility would be established. Maximizing these early experiences and results, a safeguards system of ESPF based on the concept of SBD would be designed and

  17. Licensee safeguards contingency plans

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

    The Nuclear Regulatory Commission is amending its regulations to require that licensees authorized to operate a nuclear reactor (other than certain research and test reactors), and those authorized to possess strategic quantities of plutonium, uranium-233, or uranium-235 develop and implement acceptable plans for responding to threats, thefts, and industrial sabotage of licensed nuclear materials and facilities. The plans will provide a structured, orderly, and timely response to safeguards contingencies and will be an important segment of NRC's contingency planning programs. Licensee safeguards contingency plans will result in organizing licensee's safeguards resources in such a way that, in the unlikely event of a safeguards contingency, the responding participants will be identified, their several responsibilities specified, and their responses coordinated

  18. Safeguards challenges of Fast Breeder Reactor

    International Nuclear Information System (INIS)

    Ko, H. S.

    2010-01-01

    Although the safeguards system of Sodium Fast Reactor (SFR) seems similar to that of Light Water Reactor (LWR), it was raised safeguards challenges of SFR that resulted from the visual opacity of liquid sodium, chemical reactivity of sodium and other characteristics of fast reactor. As it is the basic concept stage of the safeguards of SFR in Korea, this study tried to analyze the latest similar study of safeguards issues of the Fast Breeder Reactor (FBR) at Joyo and Monju in Japan. For this reason, this study is to introduce some potential safeguards challenges of Fast Breeder Reactor. With this analysis, future study could be to address the safeguards challenges of SFR in Korea

  19. Implementation of integrated safeguards at Nuclear Fuel Plant Pitesti, Romania

    International Nuclear Information System (INIS)

    Olaru, Vasilica; Ivana, Tiberiu; Epure, Gheorghe

    2010-01-01

    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, the opportunity exists 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 the 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 (NFP) representatives and IAEA inspectors was in June 2005. In Feb. 2007 an IAEA mission visited NFP and established the main steps for implementing the IS. There were visited the storages, technological flow, and was reviewed the disposal times for different nuclear materials, the applied chemical analysis, measuring methods, weighting method and elaborating procedure of the documents and lists. At that time the IAEA and NFP representatives established the main points for starting the IS at NFP: performing the Short Notice Random Inspections (SNRI); communication of the days established for SNRI for each year; communication of 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 deposit time for several nuclear materials i.e. advance notification (AN) for each nuclear material transfer (shipments and receipts), others. At 01 June 2007 Romania has passed officially to Integrated Safeguards and NFP (WRMD) has taken all measures to implement this objective. (authors)

  20. Safeguards can not operate alone

    International Nuclear Information System (INIS)

    Martikka, E.; Honkamaa, T.; Haemaelaeinen, M.; Okko, O.

    2013-01-01

    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

  1. IAEA safeguards for the 21st century

    International Nuclear Information System (INIS)

    1999-01-01

    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

  2. Application of safeguards procedures

    International Nuclear Information System (INIS)

    1977-01-01

    The earliest applications of safeguards procedures took place in a political and technical climate far different from that of today. In the early 1960's there was a fear of the proliferation possibilities which could arise as more and more countries acquired nuclear power plants. Today nuclear power is being produced in some 20 countries without resulting in nuclear weapons proliferation. The export of equipment and technology for the nuclear fuel cycle, however, has become the subject of current concern. In view of these developments, it is not surprising that techniques in the application of safeguards have also changed. In order to appreciate the nature of these changes, it is important to be aware of the original general attitude towards the technical problems of safeguards applications. Originally, the common attitude was that the objectives of safeguards were self-evident and the methods, while in need of development, were known at least in outline. Today, it has become evident that before a safeguards procedure can be applied, the objectives must first be carefully defined, and the criteria against which success in meeting those objectives can be measured must also be developed. In line with this change, a significant part of the effort of the safeguards inspectorate is concerned with work preliminary and subsequent to the actual inspection work in the field. Over the last two years, for example, a considerable part of the work of experienced safeguards staff has been spent in analysing the possibilities of diverting material at each facility to be safeguarded. These analyses are carried out in depth by a 'facility officer' and are subjected to constructive criticism by teams composed of staff responsible for similar types of facilities as well as other technical experts. The analyses consider the measures currently considered practicable, to meet the diversion possibilities and where necessary list the development work needed to overcome any present

  3. 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).

  4. Safeguards by Design Challenge

    International Nuclear Information System (INIS)

    Alwin, Jennifer Louise

    2016-01-01

    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).

  5. IAEA safeguards approaches and goals

    International Nuclear Information System (INIS)

    Khlebnikov, Nikolai

    2001-01-01

    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)

  6. A data management system for safeguards applications (DMSSA)

    International Nuclear Information System (INIS)

    Wu Yuan

    1994-09-01

    Implementation of the State System of Accounting for and Control of nuclear material (SSAC) in China has begun since 1989. DESSA serves as an automated tool to provide the quality Accounting Reports to the IAEA as well as to perform the data management of safeguards database. It is implemented on an IBM-compatible PC. The system is characterized as a single-user, small-scale system with cost-effective and easy-to-use feature. It consists of a data manipulating system and a database specially designed for safeguards applications. It involves several functions such as: Report Edit, Quality Control, Auditing and Data Verification, Information Retrieval and Film Management, Database Querying and so on. All functions of the system are used in an interactive mode and organized in a pull-down menu. The general design consideration of the system is that it should completely meet the requirements of the safeguards activities to provide the basis for the application of safeguards pursuant to the provisions of the Agreement between China and IAEA

  7. A data management system for safeguards applications (DMSSA)

    Energy Technology Data Exchange (ETDEWEB)

    Yuan, Wu [Beijing Inst. of Nuclear Engineering (China)

    1994-09-01

    Implementation of the State System of Accounting for and Control of nuclear material (SSAC) in China has begun since 1989. DESSA serves as an automated tool to provide the quality Accounting Reports to the IAEA as well as to perform the data management of safeguards database. It is implemented on an IBM-compatible PC. The system is characterized as a single-user, small-scale system with cost-effective and easy-to-use feature. It consists of a data manipulating system and a database specially designed for safeguards applications. It involves several functions such as: Report Edit, Quality Control, Auditing and Data Verification, Information Retrieval and Film Management, Database Querying and so on. All functions of the system are used in an interactive mode and organized in a pull-down menu. The general design consideration of the system is that it should completely meet the requirements of the safeguards activities to provide the basis for the application of safeguards pursuant to the provisions of the Agreement between China and IAEA.

  8. IAEA Safeguards: Cost/benefit analysis of commercial satellite imagery

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Christer [SSC Satellitbild AB, Kiruna (Sweden)

    1999-03-01

    A major milestone in the efforts to strengthen the Safeguards System was reached in May 1997 when the Board of Governors approved a `Model Protocol Additional to Safeguards Agreements`. The Protocol provides the legal basis necessary to enhance the Agency`s ability to detect undeclared nuclear material and activities by using information available from open sources to complement the declarations made by Member States. Commercially available high-resolution satellite data has emerged as one potential complementary open information source to support the traditional and extended Safeguard activities of IAEA. This document constitutes a first report from SSC Satellitbild giving the Agency tentative and initial estimates of the potential cost and time-savings possible with the new proposed technology. The initial cost/benefit simulation will be further finalised in the following `Implementation Blueprint` study. The general foundation and starting point for the cost/benefit calculation is to simulate a new efficient and relatively small `imagery unit` within the IAEA, capable of performing advanced image processing as a tool for various safeguards tasks. The image processing capacity is suggested to be task- and interpretation-oriented. The study was performed over a period of 1,5 weeks in late 1998, and is based upon interviews of IAEA staff, reviews of existing IAEA documentation as well as from SSC Satellitbild`s long-standing experience of satellite imagery and field missions. The cost/benefit analysis is based on a spreadsheet simulation of five potential applications of commercial satellite imagery: Reference information; Confirmation of Agency acquired and Member State supplied data; Change detection and on-going monitoring; Assessing open source information available to the Agency; Detecting undeclared activities and undeclared sites. The study confirms that the proposed concept of a relatively small `imagery unit` using high-resolution data will be a sound and

  9. Performance of a Boron-Coated-Straw-Based HLNCC for International Safeguards Applications

    Energy Technology Data Exchange (ETDEWEB)

    Simone, Angela T. [ORNL; Croft, Stephen [ORNL; McElroy, Robert Dennis [ORNL; Sun, Liang [Proportional Technologies Inc.; Hayward, Jason P. [ORNL

    2017-08-01

    3He gas has been used in various scientific and security applications for decades, but it is now in short supply. Alternatives to 3He detectors are currently being integrated and tested in neutron coincidence counter designs, of a type which are widely used in nuclear safeguards for nuclear materials assay. A boron-coated-straw-based design, similar to the High-Level Neutron Coincidence Counter-II, was built by Proportional Technologies Inc., and has been tested by the Oak Ridge National Laboratory (ORNL) at both the JRC in Ispra and ORNL. Characterization measurements, along with nondestructive assays of various plutonium samples, have been conducted to determine the performance of this coincidence counter replacement in comparison with other similar counters. This paper presents results of these measurements.

  10. Addressing Safeguards Challenges for the Future

    Energy Technology Data Exchange (ETDEWEB)

    Majali, Raed; Yim, Man-Sung [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

    2015-10-15

    IAEA safeguard system is considered the corner stone of the international nuclear nonproliferation regime. Effective implementation of this legal instrument enables the IAEA to draw a conclusion with a high degree of confidence on the peaceful use of nuclear material and activities in the state. This paper aims to provide an opportunity to address various challenges encountered by IAEA. Strengthening safeguards system for verification is one of the most urgent challenges facing the IAEA. The IAEA should be able to provide credible assurance not only about declared use of nuclear material and facilities but also about the absence of undeclared material and activities. Implementation of IAEA safeguards continue to play a vital role within the nuclear non-proliferation regime. IAEA must move towards more enhanced safeguards system that is driven by the full use of all the safeguards available relevant information. Safeguards system must be responsive to evolving challenges and continue innovation through efficient implementations of more effective safeguards.

  11. Nuclear safeguards

    International Nuclear Information System (INIS)

    Estrampres, J.

    2010-01-01

    Close cooperation with the Ministry of Industry with representation from the UNESA Safeguards Group, has meant that, after almost two years of intense meetings and negotiations, Spain has a specific plant to plant agreement for the application of Safeguards under this new method. This is an agreement which aims to be a benchmark for all other EU countries, as the IAEA tends to apply a generic agreement that, in many cases, majority interferes in the nuclear power plants own processes. (Author).

  12. Can a safeguards accountancy system really detect an unauthorized removal

    International Nuclear Information System (INIS)

    Ehinger, M.H.; Ellis, J.H.

    1981-11-01

    Theoretical investigations and system studies indicate safeguards material balance data from reprocessing plants can be used to detect unauthorized removals. Plant systems have been modeled and simulated data used to demonstrate the techniques. But how sensitive are the techniques when used with actual plant data. What is the effect of safeguards applications on plant operability. Can safeguards be acceptable to plant operators, and are there any benefits to be derived. The Barnwell Nuclear Fuel Plant (BNFP) has been devoted to answering these and other questions over the past several years. A computerized system of near-real-time accounting and in-process inventory has been implemented and demonstrated during actual plant test runs. Measured inventories and hourly material balance closures have been made to assess safeguards in an operating plant application. The tests have culminated in actual removals of material from the operating plant to investigate the response and measure the sensitivity of the safeguards and data evaluation system

  13. Implementing The Safeguards-By-Design Process

    International Nuclear Information System (INIS)

    Whitaker, J. Michael; McGinnis, Brent; Laughter, Mark D.; Morgan, Jim; Bjornard, Trond; Bean, Robert; Durst, Phillip; Hockert, John; DeMuth, Scott; Lockwood, Dunbar

    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 and 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.

  14. Optimizing IAEA Safeguards

    International Nuclear Information System (INIS)

    Varjoranta, Tero

    2016-01-01

    IAEA safeguards make a vital contribution to international security. Through safeguards, the IAEA deters the spread of nuclear weapons and provides credible assurance that States are honouring their international obligations to use nuclear material only for peaceful purposes. Its independent verification work allows the IAEA to facilitate building international confidence and strengthening collective security for all.

  15. IAEA safeguards in new nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Catton, A. [International Atomic Energy Agency, Vienna (Austria); Durbin, K. [United States Department of Energy, Washington, D.C. (United States); Hamilton, A. [International Atomic Energy Agency, Vienna (Austria); Martikka, E. [STUK, Helsinki (Finland); Poirier, S.; Sprinkle, J. K.; Stevens, R. [International Atomic Energy Agency, Vienna (Austria); Whitlock, J. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

    2014-07-01

    The inclusion of international safeguards early in the design of nuclear facilities offers an opportunity to reduce project risk. It also has the potential to minimize the impact of safeguards activities on facility operations. Safeguards by design (SBD) encourages stakeholders to become familiar with the requirements of their safeguards agreements and to decide when and how they will fulfil those requirements. As one example, modular reactors are at a design stage where SBD can have a useful impact. Modular reactors might be turnkey projects where the operator takes ownership after commissioning. This comes with a legal obligation to comply with International Atomic Energy Agency (IAEA) safeguards requirements. Some of the newcomer countries entering the reactor market have little experience with IAEA safeguards and the associated non-proliferation obligations. To reduce delays or cost increments, one can embed safeguards considerations in the bid and design phases of the project, along with the safety and security considerations. SBD does not introduce any new requirements - it is a process whereby facility designers facilitate the implementation of the existing safeguards requirements. In short, safeguards experts share their expertise with the designers and vice versa. Once all parties understand the fundamentals of all of the operational constraints, they are better able to decide how best to address them. This presentation will provide an overview of SBD activities. (author)

  16. Safeguard Vulnerability Analysis Program (SVAP)

    International Nuclear Information System (INIS)

    Gilman, F.M.; Dittmore, M.H.; Orvis, W.J.; Wahler, P.S.

    1980-01-01

    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

  17. Selected topics in special nuclear materials safeguard system design

    International Nuclear Information System (INIS)

    King, L.L.; Thatcher, C.D.; Clarke, J.D.; Rodriguez, M.P.

    1991-01-01

    During the past two decades the improvements in circuit integration have given rise to many new applications in digital processing technology by continuously reducing the unit cost of processing power. Along with this increase in processing power a corresponding decrease in circuit volume has been achieved. Progress has been so swift that new classes of applications become feasible every 2 or 3 years. This is especially true in the application of proven new technology to special nuclear materials (SNM) safeguard systems. Several areas of application were investigated in establishing the performance requirements for the SNM safeguard system. These included the improvements in material control and accountability and surveillance by using multiple sensors to continuously monitor SNM inventory within the selected value(s); establishing a system architecture to provide capabilities needed for present and future performance requirements; and limiting operating manpower exposure to radiation. This paper describes two selected topics in the application of state-of-the-art, well-proven technology to SNM safeguard system design

  18. The Systematic Approach to Training: Analysis and Evaluation in the Department of Safeguards

    International Nuclear Information System (INIS)

    Ticevic, S.; Weichselbraun, A.; Pickett, S.; Crete, J.-M.

    2015-01-01

    In applying a systematic approach to training (SAT), identifying the learning needs is the first step - a learning needs analysis allows the organization to identify the competencies required to perform a particular job. A systematic approach can provide a clear structure for training and education programme development as well as the necessary evaluation and feedback so that the organization can adjust the development accordingly and deliver the optimal learning experience. In this presentation we will describes two key elements of a SAT used in the Safeguards Training Section in the Department of Safeguards: Analysis and Evaluation. Analysis is the first part of a SAT needed to define competencies for Safeguards staff in order to improve training development within the Department. We describe the training needs analysis used to capture and articulate the various competencies required for safeguards implementation based upon an analysis of tasks and activities carried out by staff members in the Department. Firstly, we highlight the different qualitative methods used to gather information from staff and the process of evaluating and organizing this information into a structured framework. Secondly, we describe how this framework provides the necessary reference to specify learning objectives, evaluate training effectiveness, review and revise training offerings, and select appropriate training paths based on identified needs. In addition, as part of the SAT, evaluation is performed to identify the usefulness of course outcomes and improvements for future offerings based on lessons learned, to ensure that appropriate knowledge and skills are being taught and to demonstrate the value of training by meeting the organization's needs. We present how the Kirkpatrick four-level evaluation model has been implemented by Safeguards Training Section in order to evaluate course effectiveness after the training has been completed, and discuss how the current evaluation

  19. Health Information Security in Hospitals: the Application of Security Safeguards.

    Science.gov (United States)

    Mehraeen, Esmaeil; Ayatollahi, Haleh; Ahmadi, Maryam

    2016-02-01

    A hospital information system has potentials to improve the accessibility of clinical information and the quality of health care. However, the use of this system has resulted in new challenges, such as concerns over health information security. This paper aims to assess the status of information security in terms of administrative, technical and physical safeguards in the university hospitals. This was a survey study in which the participants were information technology (IT) managers (n=36) who worked in the hospitals affiliated to the top ranked medical universities (university A and university B). Data were collected using a questionnaire. The content validity of the questionnaire was examined by the experts and the reliability of the questionnaire was determined using Cronbach's coefficient alpha (α=0.75). The results showed that the administrative safeguards were arranged at a medium level. In terms of the technical safeguards and the physical safeguards, the IT managers rated them at a strong level. According to the results, among three types of security safeguards, the administrative safeguards were assessed at the medium level. To improve it, developing security policies, implementing access control models and training users are recommended.

  20. Nuclear safeguards: a perspective

    International Nuclear Information System (INIS)

    Walske, C.

    1975-01-01

    Safeguards, both international and domestic, are discussed from the industrial viewpoint. Anti-criminal measures are considered in more detail. Areas of anti-criminal safeguards which need improvement are pointed out; they include communications, recovery force, and accounting

  1. Coordinated safeguards for materials management in a mixed-oxide fuel facility

    International Nuclear Information System (INIS)

    Shipley, J.P.; Cobb, D.D.; Dietz, R.J.; Evans, M.L.; Schelonka, E.P.; Smith, D.B.; Walton, R.B.

    1977-02-01

    A coordinated safeguards system is described for safeguarding strategic quantities of special nuclear materials in mixed-oxide recycle fuel fabrication facilities. The safeguards system is compatible with industrial process requirements and combines maximum effectiveness consistent with modest cost and minimal process interference. It is based on unit process accounting using a combination of conventional and state-of-the-art NDA measurement techniques. The effectiveness of the system against single and multiple thefts is evaluated using computer modeling and simulation techniques

  2. Coordinated safeguards for materials management in a mixed-oxide fuel facility

    Energy Technology Data Exchange (ETDEWEB)

    Shipley, J.P.; Cobb, D.D.; Dietz, R.J.; Evans, M.L.; Schelonka, E.P.; Smith, D.B.; Walton, R.B.

    1977-02-01

    A coordinated safeguards system is described for safeguarding strategic quantities of special nuclear materials in mixed-oxide recycle fuel fabrication facilities. The safeguards system is compatible with industrial process requirements and combines maximum effectiveness consistent with modest cost and minimal process interference. It is based on unit process accounting using a combination of conventional and state-of-the-art NDA measurement techniques. The effectiveness of the system against single and multiple thefts is evaluated using computer modeling and simulation techniques.

  3. Reactor safeguards

    CERN Document Server

    Russell, Charles R

    1962-01-01

    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

  4. Safeguards and security research and development: Program status report, February-July 1981

    International Nuclear Information System (INIS)

    Henry, C.N.; Walton, R.B.

    1982-04-01

    This report, one of a series of biannual progress reports, describes the status of research and development in the Safeguards and Security Program at Los Alamos from February-July 1981. Most work covered here is sponsored by the Office of Safeguards and Security of the Department of Energy; however, project activities that are technically closely related to nuclear safeguards and security also are included where appropriate for conveying information useful to the nuclear community. The report comprises four major subject areas: Security Development and Support; Nuclear Materials Measurement and Engineering; Nuclear Facility Safeguards Support; and International Safeguards, Technology Transfer, and Training. Some technical topics included in the subject areas are computer and informational security, chemical and nondestructive analysis of nuclear materials, process modeling and analysis, nuclear materials accounting systems, evaluation of prototype measurement instrumentation and procedures in nuclear facilities, design and consultation for facilities, technical exchange, training courses, and international safeguards

  5. Safeguards and security research and development: Program status report, February-July 1981

    Energy Technology Data Exchange (ETDEWEB)

    Henry, C.N.; Walton, R.B. (comps.)

    1982-04-01

    This report, one of a series of biannual progress reports, describes the status of research and development in the Safeguards and Security Program at Los Alamos from February-July 1981. Most work covered here is sponsored by the Office of Safeguards and Security of the Department of Energy; however, project activities that are technically closely related to nuclear safeguards and security also are included where appropriate for conveying information useful to the nuclear community. The report comprises four major subject areas: Security Development and Support; Nuclear Materials Measurement and Engineering; Nuclear Facility Safeguards Support; and International Safeguards, Technology Transfer, and Training. Some technical topics included in the subject areas are computer and informational security, chemical and nondestructive analysis of nuclear materials, process modeling and analysis, nuclear materials accounting systems, evaluation of prototype measurement instrumentation and procedures in nuclear facilities, design and consultation for facilities, technical exchange, training courses, and international safeguards.

  6. Fully integrated safeguards and security for reprocessing plant monitoring

    International Nuclear Information System (INIS)

    Duran, Felicia Angelica; Ward, Rebecca; Cipiti, Benjamin B.; Middleton, Bobby D.

    2011-01-01

    Nuclear fuel reprocessing plants contain a wealth of plant monitoring data including material measurements, process monitoring, administrative procedures, and physical protection elements. Future facilities are moving in the direction of highly-integrated plant monitoring systems that make efficient use of the plant data to improve monitoring and reduce costs. The Separations and Safeguards Performance Model (SSPM) is an analysis tool that is used for modeling advanced monitoring systems and to determine system response under diversion scenarios. This report both describes the architecture for such a future monitoring system and present results under various diversion scenarios. Improvements made in the past year include the development of statistical tests for detecting material loss, the integration of material balance alarms to improve physical protection, and the integration of administrative procedures. The SSPM has been used to demonstrate how advanced instrumentation (as developed in the Material Protection, Accounting, and Control Technologies campaign) can benefit the overall safeguards system as well as how all instrumentation is tied into the physical protection system. This concept has the potential to greatly improve the probability of detection for both abrupt and protracted diversion of nuclear material.

  7. Building safeguards infrastructure

    International Nuclear Information System (INIS)

    McClelland-Kerr, J.; Stevens, J.

    2010-01-01

    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

  8. 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.

  9. Safeguards instrumentation: a computer-based catalog

    International Nuclear Information System (INIS)

    Fishbone, L.G.; Keisch, B.

    1981-08-01

    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

  10. Safeguards instrumentation: a computer-based catalog

    Energy Technology Data Exchange (ETDEWEB)

    Fishbone, L.G.; Keisch, B.

    1981-08-01

    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.

  11. Setting priorities for safeguards upgrades

    International Nuclear Information System (INIS)

    Al-Ayat, R.A.; Judd, B.R.; Patenaude, C.J.; Sicherman, A.

    1987-01-01

    This paper describes an analytic approach and a computer program for setting priorities among safeguards upgrades. The approach provides safeguards decision makers with a systematic method for allocating their limited upgrade resources. The priorities are set based on the upgrades cost and their contribution to safeguards effectiveness. Safeguards effectiveness is measured by the probability of defeat for a spectrum of potential insider and outsider adversaries. The computer program, MI$ER, can be used alone or as a companion to ET and SAVI, programs designed to evaluate safeguards effectiveness against insider and outsider threats, respectively. Setting the priority required judgments about the relative importance (threat likelihoods and consequences) of insider and outsider threats. Although these judgments are inherently subjective, MI$ER can analyze the sensitivity of the upgrade priorities to these weights and determine whether or not they are critical to the priority ranking. MI$ER produces tabular and graphical results for comparing benefits and identifying the most cost-effective upgrades for a given expenditure. This framework provides decision makers with an explicit and consistent analysis to support their upgrades decisions and to allocate the safeguards resources in a cost-effective manner

  12. Assurance of the effectiveness of safeguards in light of their objectives

    International Nuclear Information System (INIS)

    Kennedy, R.T.; Lyon, H.E.

    1977-01-01

    The purpose of nuclear safeguards is to prevent unauthorized use of SNM or sabotage of facilities in which significant quantities of SNM are located. A balanced safeguards system includes the three elements of material accountability, material control, and physical protection. These safeguard systems must detect unauthorized activities, initiate timely response and, as necessary, provide sufficient delay for an appropriate action to be taken. Methods used to assure effectiveness of safeguards systems for both ERDA and licensed facilities will be reviewed in this paper. The respective responsibilities of ERDA and NRC are briefly outlined as are the procedures and methods used for implementing these responsibilities. The objective of achieving overall comparability between ERDA and licensed facilities is discussed. The manner in which adequacy of safeguards is assessed is discussed. New techniques which are beginning to be employed and further refined is presented. These involve characterization of the representative threats, development of modeling of outsider and insider threats, site specific analysis of facility vulnerabilities to threats and selection of critical paths. Modeling is used to assess effectiveness with which a system protects against a postulated threat along critical attack paths. Assumptions with regard to the protection provided by the different elements can be varied to improve (decrease) vulnerability along any path. This method along with graphic analysis techniques can be used to: - Identify current weaknesses in existing or as designed systems. - Evaluate upgrading plans. - Develop design trade-offs. - Identify hardware or other developments required. Research and development is required to deal with the problems identified in these assessments and in the safeguards related studies conducted by both ERDA and NRC. These efforts and a summary of the areas currently under review will be described briefly. The practical problems of proof testing

  13. Proposals for the 1989/90 Safeguards R and D programme and associated meetings

    International Nuclear Information System (INIS)

    1987-07-01

    The R and D programme of the IAEA Department of Safeguards as carried out by or undertaken on behalf of the Division of Development and Technical Support, the Division of Safeguards Evaluation and the Division of Safeguards Information Treatment is set out in tables which give the objective of the programme elements, a description of the activities to be performed and a number of items of information required for assessment of the activities. The linkage between R and D activities and planned meetings on safeguards topics in 1989/90 is shown in a table too. 4 tabs

  14. Negotiating supranational rules. The genesis of the International Atomic Energy Agency safeguards system

    Energy Technology Data Exchange (ETDEWEB)

    Forland, A.

    1997-12-31

    The object of this study is the evolution from 1954-56 up until the mid-1970s of the nuclear safeguards system administered by the International Atomic Energy Agency (IAEA) in Vienna. The main aim of the study is not to describe the IAEA safeguards system as such. The focus will be on analysing the arguments advanced in the various negotiations, and the main objective will be to single out the factors determining the result. In the course of the time span under study two international treaties were negotiated which were decisive for the development of international nuclear safeguards. These were the IAEA Stature (1956) and the Non-Proliferation Treaty (1968). The Statue as well as the NPT contain articles on international nuclear safeguards. These articles limit themselves to spelling out the safeguards principles. It was thus left to the IAEA Board of Governors to develop the safeguards procedures in detail. Two IAEA safeguards documents were negotiated between 1959 and 1965 in order to implement the safeguards article of the Statue. The safeguards requirements of the NPT were spelled out in a new model agreement in 1972. 58 refs.

  15. Negotiating supranational rules. The genesis of the International Atomic Energy Agency safeguards system

    Energy Technology Data Exchange (ETDEWEB)

    Forland, A

    1998-12-31

    The object of this study is the evolution from 1954-56 up until the mid-1970s of the nuclear safeguards system administered by the International Atomic Energy Agency (IAEA) in Vienna. The main aim of the study is not to describe the IAEA safeguards system as such. The focus will be on analysing the arguments advanced in the various negotiations, and the main objective will be to single out the factors determining the result. In the course of the time span under study two international treaties were negotiated which were decisive for the development of international nuclear safeguards. These were the IAEA Stature (1956) and the Non-Proliferation Treaty (1968). The Statue as well as the NPT contain articles on international nuclear safeguards. These articles limit themselves to spelling out the safeguards principles. It was thus left to the IAEA Board of Governors to develop the safeguards procedures in detail. Two IAEA safeguards documents were negotiated between 1959 and 1965 in order to implement the safeguards article of the Statue. The safeguards requirements of the NPT were spelled out in a new model agreement in 1972. 58 refs.

  16. Negotiating supranational rules. The genesis of the International Atomic Energy Agency safeguards system

    International Nuclear Information System (INIS)

    Forland, A.

    1997-01-01

    The object of this study is the evolution from 1954-56 up until the mid-1970s of the nuclear safeguards system administered by the International Atomic Energy Agency (IAEA) in Vienna. The main aim of the study is not to describe the IAEA safeguards system as such. The focus will be on analysing the arguments advanced in the various negotiations, and the main objective will be to single out the factors determining the result. In the course of the time span under study two international treaties were negotiated which were decisive for the development of international nuclear safeguards. These were the IAEA Stature (1956) and the Non-Proliferation Treaty (1968). The Statue as well as the NPT contain articles on international nuclear safeguards. These articles limit themselves to spelling out the safeguards principles. It was thus left to the IAEA Board of Governors to develop the safeguards procedures in detail. Two IAEA safeguards documents were negotiated between 1959 and 1965 in order to implement the safeguards article of the Statue. The safeguards requirements of the NPT were spelled out in a new model agreement in 1972. 58 refs

  17. Safeguards and Non-destructive Assay

    International Nuclear Information System (INIS)

    Carchon, R.; Bruggeman, M.

    2001-01-01

    SCK-CEN's programme on safeguards and non-destructive assay includes: (1) various activities to assure nuclear materials accountancy; (2) contributes to the implementation of Integrated Safeguards measures in Belgium and to assist the IAEA through the Belgian Support Programme; (3) renders services to internal and external customers in the field of safeguards; (4) improves passive neutron coincidence counting techniques for waste assay and safeguards verification measurements by R and D on correlation algorithms implemented via software or dedicated hardware; (5) improves gamma assay techniques for waste assay by implementing advanced scanning techniques and different correlation algorithms; and (6) develops numerical calibration techniques. Major achievements in these areas in 2000 are reported

  18. Status and Prospect of Safeguards By Design for the Pyroprocessing Facility

    International Nuclear Information System (INIS)

    Kim, Hodong; Shin, H.S.; Ahn, S.K.

    2010-01-01

    The concept of Safeguards-By-Design (SBD), which is proposed and developed by the United States and the IAEA, is now widely acknowledged as a fundamental consideration for the effective and efficient implementation of safeguards. The application of a SBD concept is of importance especially for developmental nuclear facilities which have new technological features and relevant challenges to their safeguards approach. At this point of time, the examination of the applicability of SBD on a pyroprocessing facility, which has been being developed in the Republic of Korea (ROK), would be meaningful. The ROK developed a safeguards system with the concept of SBD for Advanced spent fuel Conditioning Process Facility (ACPF) and DUPIC Fuel Development Facility (DFDF) before the SBD concept was formally suggested. Currently. The PRIDE (PyRoprocess Integrated Inactive Demonstration) facility for the demonstration of pyroprocess using 10 ton of non-radioactive nuclear materials per year is being constructed in the ROK. The safeguards system for the facility has been designed in cooperation with a facility designer from the design phase, and the safeguards system would be established according to the future construction schedule. In preparing the design of Engineering Scale Pyroprocess Facility (ESPF), which will use spent fuels in an engineering scale and be constructed in 2016, a research on the safeguards system for this facility is also being conducted. In this connection, a project to support for development of safeguards approach for a reference pyroprocessing facility has been carried out by KAERI in cooperation with KINAC and the IAEA through an IAEA Member State Support Program (MSSP). When this MSSP project is finished in August, 2011, a safeguards system model and safeguards approach for a reference pyroprocessing facility would be established. Maximizing these early experiences and results, a safeguards system of ESPF based on the concept of SBD would be designed and

  19. Nuclear material data management and integration. A safeguard perspective

    International Nuclear Information System (INIS)

    Wilkey, David D.; Martin, H.R.; O'Leary, Jerry

    1999-01-01

    This paper is a discussion of the use of available data in the performance of nuclear material (NM) safeguards. The discussion considers the various sources of data and system requirements for collecting and managing that data, and is preliminary concerned with domestic safeguards requirements such as those specified by the US Department of Energy. The preferred configuration for integrated data management does not necessarily require a single computer system; however, separate computerized systems with direct inter-system connections is preferred. Use of all relevant data NM accounting, NM control, physical protection, and non-safeguards) is necessary to assure the most effective protection for the NM inventories. Where direct exchange of data is not possible, a systematic program to implement indirect exchange is essential [ru

  20. A lattice-valued linguistic decision model for nuclear safeguards applications

    International Nuclear Information System (INIS)

    Ruan, D.; Liu, J.; Carchon, R.

    2001-01-01

    In this study, we focus our attention on decision making models to process uncertainty-based information directly without transforming them into any particular membership function, i.e., directly using linguistic information (linguistic values) instead of numbers (numerical values). By analyzing the feature of linguistic values ordered by their means of common usage, we argue that the set of linguistic values should be characterized by a lattice structure. We propose the lattice structure based on a logical algebraic structure i.e., lattice implication algebra. Finally, we obtain a multi-objective decision-making model by extending Yager's multi-objective model from the following aspects: (1) extension of linguistic information: from a set of linear ordered linguistic labels (values) to that of lattice-valued linguistic labels; (2) extension of the combination function M, which is used to combine the individual ratings with the weights of criteria. We propose an implication operation form of M. The implication operation can be drawn from lattice implication algebra. As an illustration, we will finally apply this decision model to the evaluation problem in safeguard relevant information. (orig.)

  1. Symposium on International Safeguards: Preparing for Future Verification Challenges

    International Nuclear Information System (INIS)

    2010-01-01

    The purpose of the symposium is to foster dialogue and information exchange involving Member States, the nuclear industry and members of the broader nuclear non-proliferation community to prepare for future verification challenges. Topics addressed during the 2010 symposium include the following: - Supporting the global nuclear non-proliferation regime: Building support for strengthening international safeguards; Enhancing confidence in compliance with safeguards obligations; Legal authority as a means to enhance effectiveness and efficiency; Verification roles in support of arms control and disarmament. - Building collaboration and partnerships with other international forums: Other verification and non-proliferation regimes; Synergies between safety, security and safeguards regimes. - Improving cooperation between IAEA and States for safeguards implementation: Strengthening State systems for meeting safeguards obligations; Enhancing safeguards effectiveness and efficiency through greater cooperation; Lessons learned: recommendations for enhancing integrated safeguards implementation. - Addressing safeguards challenges in an increasingly interconnected world: Non-State actors and covert trade networks; Globalization of nuclear information and technology. - Preparing for the global nuclear expansion and increasing safeguards workload: Furthering implementation of the State-level concept and integrated safeguards; Information-driven safeguards; Remote data-driven safeguards inspections; Safeguards in States without comprehensive safeguards agreements. - Safeguarding advanced nuclear facilities and innovative fuel cycles: Proliferation resistance; Safeguards by design; Safeguards approaches for advanced facilities. - Advanced technologies and methodologies: For verifying nuclear material and activities; For detecting undeclared nuclear material and activities; For information collection, analysis and integration. - Enhancing the development and use of safeguards

  2. Safeguards agreements - their legal and conceptual basis

    International Nuclear Information System (INIS)

    Sanders, B.; Rainer, R.

    1977-01-01

    The application of Agency safeguards requires treaty arrangements (''Safeguards Agreements'') between the State or States concerned and the Agency. The authority for the Agency to conclude such agreements and to implement them is provided for in the Agency's Statute (Articles II, III A.5 and XII). On the basis of the statutory provisions safeguards principles and procedures have been elaborated. These have been laid down in: (a) The Agency's Safeguards System 1965, extended in 1966 and 1968 (INFCIRC/66/Rev.2); and (b) The basis for negotiating safeguards agreements with NNWS pursuant to NPT (INFCIRC/153). The verification of the undertaking by the State concerned not to use items subject to safeguards for purposes contrary to the terms of the agreement is verified through the application of various safeguards measures (design review, records, reports and inspection). Containment and surveillance measures are expected to play an increasingly important role. NPT Safeguards Agreements foresee as one of their specific features the establishment of national systems of accounting and control of nuclear material. The majority of the agreements concluded under document INFCIRC/66/Rev.2 - i.e. the non-NPT safeguards agreements - implement obligations undertaken under co-operation agreements between States for peaceful uses of nuclear energy. These agreements naturally reflect approaches adopted by the parties, in particular as to the circumstances under which safeguards should be applied. Thus, the concepts used in the non-NPT safeguards agreements and the safeguards system of document INFCIRC/66/Rev.2 which is incorporated in these agreements by reference are in continuous evolution. Document INFCIRC/66/Rev.2 continues to be supplemented in practical application and through explicit decision by the Board. The non-NPT safeguards agreements contain, besides technical safeguards provisions from document INFCIRC/66/Rev.2, and further provision for notification, inventories

  3. Safeguards Strategy in Physical Protection System for Nuclear Installation

    International Nuclear Information System (INIS)

    Ade lndra B; Kasturi; Tatang Eryadi

    2004-01-01

    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)

  4. Safeguards technology: present posture and future impact

    International Nuclear Information System (INIS)

    Keepin, G.R.

    1976-01-01

    With widespread and growing concern over the issues of nuclear safeguards, international nuclear trade and nuclear weapons proliferation, the full development of the world's nuclear energy potential could well depend on how effectively the strategic nuclear materials that fuel nuclear power are controlled and safeguarded. The broad U.S. program in nuclear safeguards and security is directed toward a balanced safeguards system incorporating the two major components of physical security and materials control. The current posture of modern safeguards technology, its impact on plant operations, and the key role it must play in the implementation of stringent cost-effective safeguards systems in facilities throughout the nuclear fuel cycle are outlined

  5. A view to the new safeguards system

    International Nuclear Information System (INIS)

    Tsuboi, Hiroshi

    2000-01-01

    The Additional Protocol to the Safeguards Agreement between Japan and the IAEA entered into force on 16 December 1999. An initial declaration of the expanded information will be provided to the IAEA by next June in accordance with the Additional Protocol. In Japan the new integrated safeguards system, which strengthens the effectiveness and improves efficiency of IAEA Safeguards, is considered to be very important issue. The establishment of a permanent and universal safeguards system including application of safeguards in Nuclear Weapon States also is an important issue from the view-point of not only non-proliferation but also nuclear disarmament. Safeguards are expected to have an increasingly important role. (author)

  6. Modeling of UF{sub 6} enrichment with gas centrifuges for nuclear safeguards activities

    Energy Technology Data Exchange (ETDEWEB)

    Mercurio, G.; Peerani, P.; Richir, P.; Janssens, W.; Eklund, G. [European Commission, Joint Research Centre, Institute for Transuranium Elements Via Fermi, 2749-TP181,20127 Ispra (Italy)

    2012-09-26

    The physical modeling of uranium isotopes ({sup 235}U, {sup 238}U) separation process by centrifugation of is a key aspect for predicting the nuclear fuel enrichment plant performances under surveillance by the Nuclear Safeguards Authorities. In this paper are illustrated some aspects of the modeling of fast centrifuges for UF{sub 6} gas enrichment and of a typical cascade enrichment plant with the Theoretical Centrifuge and Cascade Simulator (TCCS). The background theory for reproducing the flow field characteristics of a centrifuge is derived from the work of Cohen where the separation parameters are calculated using the solution of a differential enrichment equation. In our case we chose to solve the hydrodynamic equations for the motion of a compressible fluid in a centrifugal field using the Berman - Olander vertical velocity radial distribution and the solution was obtained using the Matlab software tool. The importance of a correct estimation of the centrifuge separation parameters at different flow regimes, lies in the possibility to estimate in a reliable way the U enrichment plant performances, once the separation external parameters are set (feed flow rate and feed, product and tails assays). Using the separation parameters of a single centrifuge allow to determine the performances of an entire cascade and, for this purpose; the software Simulink was used. The outputs of the calculation are the concentrations (assays) and the flow rates of the enriched (product) and depleted (tails) gas mixture. These models represent a valid additional tool, in order to verify the compliance of the U enrichment plant operator declarations with the 'on site' inspectors' measurements.

  7. Strategic plan for the development of IAEA safeguards equipment

    International Nuclear Information System (INIS)

    Khlebnikov, N.

    2001-01-01

    Full text: The need for a top-down Safeguards Strategy to focus departmental objectives was recognized by the Programme Performance Appraisal System (PPAS) performed on the Equipment Development Project in 1999. The Department of Safeguards prepared at the end of 2000 a 5-year Strategic Plan to identify the changes and improvements expected to take place over the 2001-2005 period. Those Strategic Objectives were supposed to be used to properly plan IAEA Safeguards activities and define appropriate and coherent R and D programmes. The present paper describes the strategic directions that the IAEA will follow in the area of equipment development in order to meet the Safeguards Department long-term objectives for 2001-2005. The paper, which is derived from the IAEA Strategic Equipment Development Plan, prepared by the Division of Technical Support, includes two parts: general principles and policies applicable to all equipment development tasks; specific strategic guidance. The paper will not describe the detailed plans which are prepared based on the strategic plan on a biannual basis. Equipment development activities have been divided in five major projects (NDA, Seals, Surveillance, Unattended Monitoring and Remote Monitoring). Strategic directions for each of these projects will be described in the paper. Separate sections will deal with equipment development strategic guidance in the area of additional protocol inspections, JNFL projects, illicit trafficking and Trilateral Initiative. (author)

  8. Safeguards training at Pacific Northwest Laboratory

    International Nuclear Information System (INIS)

    Dickman, D.A.

    1986-10-01

    Safeguarding our country's nuclear materials against theft or diversion is extremely important due to their significantly strategic value. In addition, nuclear materials also have an extremely high monetary value. The term ''safeguards'' is defined as an integrated system of physical protection, accountability, and material control measures designed to deter, prevent, detect, and respond to unauthorized possession and use of special nuclear materials. An aggressive Safeguards program, therefore, employs both good security measures and a strong material control and accountability system. For effective internal control of nuclear materials, having people qualified in the many aspects of safeguards and accountability is essential. At Pacific Northwest Laboratory (PNL), this goal is accomplished through a Laboratory-wide Safeguards Awareness Program. All PNL staff members receive a level of Safeguards training appropriate to their particular function within the Laboratory. This paper presents an overview of the unique training opportunities this topic provides and how the training goals are accomplished through the various training courses given to the staff members

  9. Safeguards research: assessing material control and accounting systems

    International Nuclear Information System (INIS)

    Maimoni, A.

    1977-01-01

    The Laboratory is working for the Nuclear Regulatory Commission to improve the safeguarding of special nuclear material at nuclear fuel processing facilities, to provide a basis for improved regulations for material control and accounting systems, and to develop an assessment procedure for verifying compliance with these regulations. Early work included setting up a hierarchy of safeguard objectives and a set of measurable parameters with which systems performance to meet those objectives can be measured. Present work has focused on developing a computerized assessment procedure. We have also completed a test bed (based on a plutonium nitrate storage area) to identify and correct problems in the procedure and to show how this procedure can be used to evaluate the performance of an applicant's material control and accounting system

  10. The evolution of safeguards

    International Nuclear Information System (INIS)

    Heinonen, O.

    1999-01-01

    The Agency's safeguards system has demonstrated a flexibility capable of responding to the verification demands of its Member States. It is capable of safeguarding nuclear materials, facilities, equipment and non-nuclear material. The Agency is in the process of strengthening safeguards in its verification of declared activities. Since the early 1990's the Board of Governors took up the issue of strengthening measures such as inspections at undeclared locations, the early provision of design information, a system of universal reporting on nuclear material and certain nuclear-related equipment and non-nuclear material. Following the Agency's 'Programme 93+2', a major step forward was the adoption by the Board of Governors of the Additional Protocol in May 1997. This included important strengthened safeguards measures based on greater access to information and locations. A number of member states have already indicated their willingness to participate in this system by signing the Additional Protocol and this is now in the early stages of implementation for a few states. (author)

  11. Safeguards on nuclear materials

    International Nuclear Information System (INIS)

    Cisar, V.; Keselica, M.; Bezak, S.

    2001-01-01

    The article describes the implementation of IAEA safeguards for nuclear materials in the Czech and Slovak Republics, the establishment and development of the State System of Accounting for and Control of Nuclear Material (SSAC) at the levels of the state regulatory body and of the operator, particularly at the Dukovany nuclear power plant. A brief overview of the historical development is given. Attention is concentrated on the basic concepts and legal regulation accepted by the Czech and Slovak Republics in accordance with the new approach to create a complete legislative package in the area of nuclear energy uses. The basic intention is to demonstrate the functions of the entire system, including safeguards information processing and technical support of the system. Perspectives of the Integrated Safeguards System are highlighted. The possible ways for approximation of the two national systems to the Safeguards System within the EU (EURATOM) are outlined, and the necessary regulatory and operators' roles in this process are described. (author)

  12. INSTITUTIONALIZING SAFEGUARDS-BY-DESIGN: HIGH-LEVEL FRAMEWORK

    Energy Technology Data Exchange (ETDEWEB)

    Trond Bjornard PhD; Joseph Alexander; Robert Bean; Brian Castle; Scott DeMuth, Ph.D.; Phillip Durst; Michael Ehinger; Prof. Michael Golay, Ph.D.; Kevin Hase, Ph.D.; David J. Hebditch, DPhil; John Hockert, Ph.D.; Bruce Meppen; James Morgan; Jerry Phillips, Ph.D., PE

    2009-02-01

    participation in facility design options analysis in the conceptual design phase to enhance intrinsic features, among others. The SBD process is unlikely to be broadly applied in the absence of formal requirements to do so, or compelling evidence of its value. Neither exists today. A formal instrument to require the application of SBD is needed and would vary according to both the national and regulatory environment. Several possible approaches to implementation of the requirements within the DOE framework are explored in this report. Finally, there are numerous barriers to the implementation of SBD, including the lack of a strong safeguards culture, intellectual property concerns, the sensitive nature of safeguards information, and the potentially divergent or conflicting interests of participants in the process. In terms of SBD implementation in the United States, there are no commercial nuclear facilities that are under IAEA safeguards. Efforts to institutionalize SBD must address these issues. Specific work in FY09 could focus on the following: finalizing the proposed SBD process for use by DOE and performing a pilot application on a DOE project in the planning phase; developing regulatory options for mandating SBD; further development of safeguards-related design guidance, principles and requirements; development of a specific SBD process tailored to the NRC environment; and development of an engagement strategy for the IAEA and other international partners.

  13. INSTITUTIONALIZING SAFEGUARDS-BY-DESIGN: HIGH-LEVEL FRAMEWORK

    International Nuclear Information System (INIS)

    Bjornard, Trond; Alexander, Joseph; Bean, Robert; Castle, Brian; DeMuth, Scott; Durst, Phillip; Ehinger, Michael; Golay, Michael; Hase, Kevin; Hebditch, David J.; Hockert, John; Meppen, Bruce; Morgan, James; Phillips, Jerry

    2009-01-01

    facility design options analysis in the conceptual design phase to enhance intrinsic features, among others. The SBD process is unlikely to be broadly applied in the absence of formal requirements to do so, or compelling evidence of its value. Neither exists today. A formal instrument to require the application of SBD is needed and would vary according to both the national and regulatory environment. Several possible approaches to implementation of the requirements within the DOE framework are explored in this report. Finally, there are numerous barriers to the implementation of SBD, including the lack of a strong safeguards culture, intellectual property concerns, the sensitive nature of safeguards information, and the potentially divergent or conflicting interests of participants in the process. In terms of SBD implementation in the United States, there are no commercial nuclear facilities that are under IAEA safeguards. Efforts to institutionalize SBD must address these issues. Specific work in FY09 could focus on the following: finalizing the proposed SBD process for use by DOE and performing a pilot application on a DOE project in the planning phase; developing regulatory options for mandating SBD; further development of safeguards-related design guidance, principles and requirements; development of a specific SBD process tailored to the NRC environment; and development of an engagement strategy for the IAEA and other international partners.

  14. Defining and Measuring Safeguards Culture

    International Nuclear Information System (INIS)

    Frazar, Sarah L.; Mladineo, Stephen V.

    2010-01-01

    In light of the shift toward State Level Evaluations and information driven safeguards, this paper offers a refined definition of safeguards culture and a set of metrics for measuring the extent to which a safeguards culture exists in a state. Where the IAEA is able to use the definition and metrics to come to a positive conclusion about the country, it may help reduce the burden on the Agency and the state.

  15. IAEA Safeguards Information System (ISIS)

    International Nuclear Information System (INIS)

    1984-10-01

    Publication of this technical document should serve for better understanding of the technical and functional features of the IAEA Safeguards Information System (ISIS) within the Agency, as well as in the National Systems of accounting for and control of nuclear material. It will also serve as a foundation for further development and improvement of the design and modifications of the Safeguards Information System and its services as a function of Safeguards implementation

  16. Measuring the safeguards value of material accountability

    International Nuclear Information System (INIS)

    Sicherman, A.

    1988-01-01

    Material accountability (MA) activities focus on providing after-the-fact indication of diversion or theft of special nuclear material (SNM). MA activities include maintaining records for tracking nuclear material and conducting periodic inventories and audits to ensure that loss has not occurred. This paper presents a value model concept for assessing the safeguards benefits of MA activities and for comparing these benefits to those provided by physical protection (PP) and material control (MC) components. The model considers various benefits of MA, which include: 1) providing information to assist in recovery of missing material, 2) providing assurance that physical protection and material control systems have been working, 3) defeating protracted theft attempts, and 4) properly resolving causes of and responding appropriately to anomalies of missing material and external alarms (e.g., hoax). Such a value model can aid decision-makers in allocating safeguards resources among PP, MC, and MA systems

  17. Information-Driven Safeguards: A Country Officer's Perspective

    International Nuclear Information System (INIS)

    Gyane, E.

    2010-01-01

    Since the transition from 'traditional' to strengthened safeguards, the evaluation and analysis of information has played an increasingly important role in the Agency's safeguards activities. During the State evaluation process, the Agency utilizes all available information for drawing credible safeguards conclusions. Besides State declared information and data gathered during inspections, a large number of information sources are reviewed for any indications of safeguards relevance. The State level approach - in contrast to the facility-based approach under traditional safeguards - considers the acquisition paths available to a State and adjusts safeguards intensity accordingly. An additional protocol widens the information base available to the Agency for analysis and evaluation and it extends the Agency's access rights in the field. The use of information for determining safeguards activities is often referred to as 'information-driven safeguards'. Country officers are inspectors in the Department of Safeguards Operations Divisions who are responsible for States and thus form the base of the Agency's information chain. The information-driven safeguards approach has led to a significant change in the role of inspector country officers: While the verification of declared nuclear material remains the cornerstone of the IAEA Safeguards System, country officers are now not only expected to be knowledgeable about the inspection-related aspects in their countries. They also need to act on information on their States coming from a variety of sources on an ongoing basis, in order to identify proliferation indicators at an early stage. Country officers thus analyse developments in their States as well as their States' relations with other States. They review scientific literature for research that could potentially be of safeguards relevance. They observe their States' nuclear facilities from satellite imagery. They evaluate reports on nuclear trade between their States

  18. International inspection activity impacts upon DOE safeguards requirements

    International Nuclear Information System (INIS)

    Zack, N.R.

    1995-01-01

    The US has placed certain special nuclear materials declared excess to their strategic needs under international safeguards through the International Atomic Energy Agency (IAEA). This Presidential initiative has obligated materials at several Department of Energy (DOE) facilities for these safeguards activities to demonstrate the willingness of the US to ban production or use of nuclear materials outside of international safeguards. However, IAEA inspection activities generally tend to be intrusive in nature and are not consistent with several domestic safeguards procedures implemented to reduce worker radiation exposures and increase the cost-effectiveness and efficiency of accounting for and storing of special nuclear materials. To help identify and provide workable solutions to these concerns, the Office of Safeguards and Security has conducted a program to determine possible changes to the DOE safeguards and security requirements designed to help facilities under international safeguards inspections more easily comply with domestic safeguards goals during international inspection activities. This paper will discuss the impact of international inspection activities on facility safeguards operations and departmental safeguards procedures and policies

  19. Application of EMCAS timeliness model to the safeguards/facility interface

    International Nuclear Information System (INIS)

    Eggers, R.F.; Giese, E.W.

    1987-01-01

    The Hanford operating contractor has developed a timeliness model for periodic mass balance tests (MBTs) for loss of special nuclear material (SNM). The purpose of the model is to compute the probability that an adversary will be detected by a periodic MBT before he could escape from a facility with stolen SNM using stealth and deceit to avoid detection. The model considers (a) the loss detection sensitivity of the MBT, (b) the time between MBTs, and (c) the statistical distribution of the total time required to complete stealth and deceit strategies. The model shows whether or not it is cost-effective to conduct frequent MBTs for loss and where improvements should be made. The Evaluation Methods for Material Control and Accountability Safeguards Systems (EMCAS) timeliness model computes the loss detection capability of periodic materials control and accounting (MC ampersand A) tests in terms of (a) the ability of the test to detect the specified target quantity and (b) the probability that the MC ampersand A test will occur before the adversary can complete the sequence of stealth and deceit strategies required to avoid detection

  20. A safeguards program for implementing Department of Energy requirements

    International Nuclear Information System (INIS)

    Erkkila, B.H.

    1989-01-01

    The U.S. Department of Energy (DOE) issued a new materials control and accountability (MC ampersand A) order 5633.3 in February of 1988. This order contains all of the requirements for an effective MC ampersand A (safeguards) program for facilities that control and account for nuclear materials in their operations. All contractors were expected to come into compliance with the order by April 30, 1989, or obtain approval for exceptions and/or extensions. The order also contains various performance requirements that are not in effect until the DOE issues the guidelines to the performance requirements. After evaluations were completed in February 1989, it was determined there were several deficiencies in the Los Alamos National Laboratory's (LANL's) safeguards program. Documentation of policy and procedures needed correction before LANL could be in compliance with the new MC ampersand A order. Differences between the old and new orders were addressed. After this determination, action teams were established to corrected LANL's safeguards program. Compliance with the DOE requirements was the goal of this activity. The accomplishments of the action teams are the subject of this paper

  1. MACSSA (Macintosh Safeguards Systems Analyzer)

    International Nuclear Information System (INIS)

    Argentesi, F.; Costantini, L.; Kohl, M.

    1986-01-01

    This paper discusses MACSSA a fully interactive menu-driven software system for accountancy of nuclear safeguards systems written for Apple Macintosh. Plant inventory and inventory change records can be entered interactively or can be downloaded from a mainframe database. Measurement procedures and instrument parameters can be defined. Partial or total statistics on propagated errors is performed and shown in tabular or graphic form

  2. Human as a component of a nuclear material safeguard system

    International Nuclear Information System (INIS)

    Morgan, D.E.; Schechter, R.S.

    1978-01-01

    Many human vigilance experiments are summarized and principles are extracted which should be useful in designing and evaluating a nuclear material safeguard system. A human is a poor observer and is not a dependable part of any man-machine system when required to function as an observer. There are a few techniques which improve his performance by providing feedback. A conceptual model is presented which is helpful in design and evaluation of systems. There is some slight experimental support for the model. Finally, some techniques of time study and statistical control charting will be useful as a means of detecting nuclear diversion attempts

  3. Safeguards techniques and equipment. 2003 ed

    International Nuclear Information System (INIS)

    2003-01-01

    nuclear activities. Development of equipment and techniques for safeguards is continuing with the help of national support programmes that assist the IAEA in keeping pace with the evolution of new technology. The IAEA defines the safeguards needs, co-ordinates the support programmes, and tests and evaluates the techniques and the resulting equipment being developed. All aspects of equipment performance are evaluated, including compliance with specifications, reliability and transportability and, most importantly, suitability for use by IAEA inspectors in nuclear facilities. The IAEA has an established quality assurance procedure to authorize equipment and software for routine inspection use. The equipment and techniques highlighted in this booklet are those in frequent use for inspection purposes or in the late stages of development. The overall objective of this publication is to provide a comprehensive overview of the techniques and equipment underlying the implementation of IAEA safeguards

  4. Introduction to nuclear material safeguards

    International Nuclear Information System (INIS)

    Kuroi, Hideo

    1986-01-01

    This article is aimed at outlining the nuclear material safeguards. The International Atomic Energy Agency (IAEA) was established in 1957 and safeguards inspection was started in 1962. It is stressed that any damage resulting from nuclear proliferation would be triggered by a human intentional act. Various measures have been taken by international societies and nations, of which the safeguards are the only means which relay mainly on technical procedures. There are two modes of diversing nuclear materials to military purposes. One would be done by national intension while the other by indivisulas or expert groups, i.e., sub-national intention. IAEA is responsible for the prevention of diversification by nations, for which the international safeguards are being used. Measures against the latter mode of diversification are called nuclear protection, for which each nation is responsible. The aim of the safeguards under the Nonproliferation Treaty is to detect the diversification of a significant amount of nuclear materials from non-military purposes to production of nuclear explosion devices such as atomic weapons or to unidentified uses. Major technical methods used for the safeguards include various destructive and non-destructive tests as well as containment and monitoring techniques. System techniques are to be employed for automatic containment and monitoring procedures. Appropriate nuclear protection system techniques should also be developed. (Nogami, K.)

  5. Next Generation Safeguards Initiative: 2010 and Beyond

    International Nuclear Information System (INIS)

    Whitney, J.M.; LaMontagne, S.; Sunshine, A.; Lockwood, D.; Peranteau, D.; Dupuy, G.

    2010-01-01

    Strengthening the international safeguards system is a key element of the U.S. non-proliferation policy agenda as evidenced by President Obama's call for more 'resources and authority to strengthen international inspections' in his April 2009 Prague speech. Through programs such as the recently-launched Next Generation Safeguards Initiative (NGSI) and the long standing U.S. Program of Technical Assistance to IAEA Safeguards, the United States is working to implement this vision. The U.S. Department of Energy's National Nuclear Security Administration launched NGSI in 2008 to develop the policies, concepts, technologies, expertise, and international safeguards infrastructure necessary to strengthen and sustain the international safeguards system as it evolves to meet new challenges. Following a successful 2009, NGSI has made significant progress toward these goals in 2010. NGSI has recently completed a number of policy studies on advanced safeguards concepts and sponsored several workshops, including a second international meeting on Harmonization of International Safeguards Infrastructure Development in Vienna. The program is also continuing multi-year projects to investigate advanced non-destructive assay techniques, enhance recruitment and training efforts, and strengthen international cooperation on safeguards. In December 2010, NGSI will host the Third Annual International Meeting on International Safeguards in Washington, DC, which will draw together key stakeholders from government, the nuclear industry, and the IAEA to further develop and promote a common understanding of Safeguards by Design principles and goals, and to identify opportunities for practical application of the concept. This paper presents a review of NGSI program activities in 2010 and previews plans for upcoming activities. (author)

  6. Verification and the safeguards legacy

    International Nuclear Information System (INIS)

    Perricos, Demetrius

    2001-01-01

    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

  7. Development and application of a safeguards system in a fabrication plant for highly enriched uranium

    International Nuclear Information System (INIS)

    Cuypers, M.; Stricht, E. van der

    1979-01-01

    This paper gives a general view of the safeguards activities performed at the Nukem Fabrication plant (Hanau, Federal Republic of Germany) during the last seven years. The main safeguards-relevant features of the plant are given and discussed. The importance is stressed of a good working relationship between the three principal partners, viz. the operator, the safeguards authority and the latter's technical support service. The definition, implementation and improvement of safeguards equipment and activities are outlined. The paper describes the internal organization established by the operator to fulfil his responsibilities, the safeguards philosophy, the Non-Destructive Assay equipment permanently installed by Euratom Safeguards, the results obtained, and the evaluation of the material balances. Conclusions are drawn (and specific comments made throughout the paper) from the experience gained over this period of seven years. (author)

  8. Engineered safeguards system activities at Sandia Laboratories for back-end fuel cycle facilities

    International Nuclear Information System (INIS)

    Sellers, T.A.; Fienning, W.C.; Winblad, A.E.

    1978-01-01

    Sandia Laboratories have been developing concepts for safeguards systems to protect facilities in the back-end of the nuclear fuel cycle against potential threats of sabotage and theft of special nuclear material (SNM). Conceptual designs for Engineered Safeguards Systems (ESSs) have been developed for a Fuel Reprocessing Facility (including chemical separations, plutonium conversion, and waste solidification), a Mixed-Oxide Fuel Fabrication Facility, and a Plutonium Transport Vehicle. Performance criteria for the various elements of these systems and a candidate systematic design approach have been defined. In addition, a conceptual layout for a large-scale Fuel-Cycle Plutonium Storage Facility has been completed. Work is continuing to develop safeguards systems for spent fuel facilities, light-water reactors, alternative fuel cycles, and improved transportation systems. Additional emphasis will be placed on the problems associated with national diversion of special nuclear material. The impact on safeguards element performance criteria for surveillance and containment to protect against national diversion in various alternative fuel cycle complexes is also being investigated

  9. Network adaptable information systems for safeguard applications

    International Nuclear Information System (INIS)

    Rodriguez, C.; Burczyk, L.; Chare, P.; Wagner, H.

    1996-01-01

    While containment and surveillance systems designed for nuclear safeguards have greatly improved through advances in computer, sensor, and microprocessor technologies, the authors recognize the need to continue the advancement of these systems to provide more standardized solutions for safeguards applications of the future. The benefits to be gained from the use of standardized technologies are becoming evident as safeguard activities are increasing world-wide while funding of these activities is becoming more limited. The EURATOM Safeguards Directorate and Los Alamos National Laboratory are developing and testing advanced monitoring technologies coupled with the most efficient solutions for the safeguards applications of the future

  10. IAEA safeguards - a 1988 perspective

    International Nuclear Information System (INIS)

    Jennekens, J.

    1988-01-01

    The problem of IAEA safeguards as regards its perspectives for 1988 is discussed. The necessity of balancing between safeguards measures required for the timely detection of nuclear material diversion to military purposes and measures to prove the absence of diversion is stated. Accurately working safeguards system aimed at the provision of nondiversion can include, as an accompanying component, any deterrence element required. Such a system will be more expensive than any other altrenatives but it will undoubtly be more suitable and accepatble

  11. Performance evaluation of a commercially available heat flow calorimeter and applicability assessment for safeguarding special nuclear materials

    International Nuclear Information System (INIS)

    Bracken, D.S.; Biddle, R.; Rudy, C.

    1998-01-01

    The performance characteristics of a commercially available heat-flow calorimeter will be presented. The heat-flow sensors within the calorimeter are based on thermopile technology with a vendor-quoted sensitivity of 150 microV/mW. The calorimeter is a full-twin design to compensate for ambient temperature fluctuations. The efficacy of temperature fluctuation compensations will also be detailed. Finally, an assessment of design applicability to special nuclear materials control and accountability and safeguarding will be presented

  12. Pickering safeguards: a preliminary analysis

    International Nuclear Information System (INIS)

    Todd, J.L.; Hodgkinson, J.G.

    1977-05-01

    A summary is presented of thoughts relative to a systems approach for implementing international safeguards. Included is a preliminary analysis of the Pickering Generating Station followed by a suggested safeguards system for the facility

  13. Scientific data base for safeguards components

    International Nuclear Information System (INIS)

    Hall, R.C.; Jones, R.D.

    1978-01-01

    The need to store and maintain vast amounts of data and the desire to avoid nonfunctional redundancy have provided an impetus for modern data base technology. Large-scale data base management systems (DBMS) have emerged during the past two decades evolving from earlier generalized file processing systems. This evolution has primarily involved certain business applications (e.g., production control, payroll, order entry) because of their high volume data processing characterization. Current data base technology, however, is becoming increasingly concerned with generality. Many diverse applications, including scientific ones, are benefiting from the generalized data base management software which has resulted. The concept of a data base management system is examined. The three common models which have been proposed for organizing data and relationships are identified: the network model, the hierarchical model, and the relational model. A specific implementation using a hierarchical data base management system is described. This is the data base for safeguards components which has been developed at Sandia Laboratories using the System 2000 developed by MRI Systems Corporation. Its organization, components, and functions are presented. The various interfaces it permits to user programs (e.g., safeguards automated facility evaluation software) and interactive terminal users are described

  14. Overcoming Safeguards Challenges

    International Nuclear Information System (INIS)

    Henriques, Sasha

    2011-01-01

    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

  15. DESIGN INFORMATION VERIFICATION FOR NUCLEAR SAFEGUARDS

    Energy Technology Data Exchange (ETDEWEB)

    Robert S. Bean; Richard R. M. Metcalf; Phillip C. Durst

    2009-07-01

    A critical aspect of international safeguards activities performed by the International Atomic Energy Agency (IAEA) is the verification that facility design and construction (including upgrades and modifications) do not create opportunities for nuclear proliferation. These Design Information Verification activities require that IAEA inspectors compare current and past information about the facility to verify the operator’s declaration of proper use. The actual practice of DIV presents challenges to the inspectors due to the large amount of data generated, concerns about sensitive or proprietary data, the overall complexity of the facility, and the effort required to extract just the safeguards relevant information. Planned and anticipated facilities will (especially in the case of reprocessing plants) be ever larger and increasingly complex, thus exacerbating the challenges. This paper reports the results of a workshop held at the Idaho National Laboratory in March 2009, which considered technologies and methods to address these challenges. The use of 3D Laser Range Finding, Outdoor Visualization System, Gamma-LIDAR, and virtual facility modeling, as well as methods to handle the facility data issues (quantity, sensitivity, and accessibility and portability for the inspector) were presented. The workshop attendees drew conclusions about the use of these techniques with respect to successfully employing them in an operating environment, using a Fuel Conditioning Facility walk-through as a baseline for discussion.

  16. Safeguarding arms control

    International Nuclear Information System (INIS)

    Flanagan, S.J.

    1988-01-01

    This essay reviews the evolution of various safeguards concepts associated with U.S. Soviet arms control negotiations over the past twenty-five years. It explore in some detail the origins, nature, and effectiveness of the safeguards packages associated with six agreements: the Limited Test Ban Treaty (1963), the SALT I Interim Agreement (1972), the Anti-Ballistic Missile (ABM) Treaty (1972), the Threshold Test Ban Treaty (1974), the Peaceful Nuclear Explosions Treaty (1976) and the SALT II Treaty (1979). Finally, the implications of this historical record for developing future nuclear and conventional arms control accords and for shoring up existing pacts, such as the ABM Treaty, are assessed with a view towards practicable prescriptions for Western policymakers. The treaty eliminating intermediate-range nuclear forces (INF) incorporates several verification safeguards, and it is very likely that analogous measures would be attached to any accord constraining conventional forces in Europe

  17. Safeguards Export-Import Training: Adapting to Changes in the Department of Safeguards Over 6 Years of Experience

    International Nuclear Information System (INIS)

    Chatelus, R.; ); Crete, J.-M.; Schot, P.-M.; Hushbeck, E.C.; Heine, P.

    2015-01-01

    Safeguards relevant information encompasses information available to the Agency in exercising its rights and fulfiling its obligations under relevant safeguards agreement(s). It includes information relating to nuclear or nuclear related trade like international transfers of nuclear material, or export (or import upon request by the Agency) of specified equipment described in annex 2 of the Additional Protocol. It may also include information provided by States on a voluntary basis. In 2005, the General Conference (see GC(49)/RES/13) encouraged the provision of information on procurement enquiries, export denials and other nuclear related information. Objectively and independently assessing this information and combining it with other Safeguards data and knowledge requires relevant expertise and well defined processes. Since 2008, the bi-annual Export-Import (EXIM) Training Workshop, jointly run by the IAEA Department of Safeguards and the U.S. Department of Energy, enables SG staff to develop competencies required for collecting, processing and drawing objective conclusions in this area. Over the years, more than 150 SG staff have been exposed to technical information on relevant non-nuclear material and equipment, trade data from different origins, analytical processes, and exercises to use this knowledge in realistic safeguards work scenarios. The EXIM training has also been an opportunity to develop analytical best practices and explore how this analytical work finds it place in the verification process. The paper describes the background and purpose of the EXIM training, how it helps Safeguards to independently collect and analyze relevant trade information to fulfil its obligations. It also touches on the lessons learned from six years of training experience, observing how the Department of Safeguards develops and implements structured processes to collect, process and evaluate safeguards relevant trade information, in order to establish findings and draw

  18. Optimizing the IAEA safeguards system

    International Nuclear Information System (INIS)

    Drobysz, Sonia; Sitt, Bernard

    2011-09-01

    During the 2010 Non-Proliferation Treaty Review Conference, States parties recognized that the Additional Protocol (AP) provides increased confidence about the absence of undeclared nuclear material and activities in a State as a whole. They agreed in action 28 of the final document to encourage 'all States parties that have not yet done so to conclude and bring into force an AP as soon as possible and to implement them provisionally pending their entry into force'. Today, 109 out of 189 States parties to the NPT have brought an AP in force. The remaining outliers have not yet done so for three types of reasons: they do not clearly understand what the AP entails; when they do, they refuse to accept new non-proliferation obligations either on the ground of lack of progress in the realm of disarmament, or simply because they are not ready to bear the burden of additional safeguards measures. Strong incentives are thus needed in order to facilitate universalization of the AP. While external incentives would help make the AP a de facto norm and encourage its conclusion by reducing the deplored imbalanced implementation of non-proliferation and disarmament obligations, internal incentives developed by the Agency and its member States can also play an important role. In this respect, NPT States parties recommended in action 32 of the Review Conference final document 'that IAEA safeguards should be assessed and evaluated regularly. Decisions adopted by the IAEA policy bodies aimed at further strengthening the effectiveness and improving the efficiency of IAEA safeguards should be supported and implemented'. The safeguards system should therefore be optimized: the most effective use of safeguards measures as well as safeguards human, financial and technical resources would indeed help enhance the acceptability and even attractiveness of the AP. Optimization can be attractive for States committed to a stronger verification regime independently from other claims, but still

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

    International Nuclear Information System (INIS)

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

    2010-01-01

    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

  20. Safeguards Implementation Guide for States with Small Quantities Protocols

    International Nuclear Information System (INIS)

    2013-01-01

    The International Atomic Energy Agency (IAEA) works to enhance the contribution of nuclear energy for peace and prosperity around the world, while helping to ensure that nuclear material is not diverted to nuclear weapons or other nuclear explosive devices. In implementing safeguards, the IAEA plays an instrumental independent verification role, providing credible assurances that States' safeguards commitments are being respected. Most of the world's non-nuclear-weapon States (NNWSs) have concluded comprehensive safeguards agreements (CSAs) with the IAEA, pursuant to the Treaty on the Non- Proliferation of Nuclear Weapons (NPT). The IAEA and States are required to cooperate in the implementation of such agreements. Effective cooperation demonstrates a State's commitment to the peaceful use of nuclear energy and furthers the State's national interests by reducing the risk of unauthorized use of nuclear material. Over 100 NNWSs party to the NPT have very limited quantities of nuclear material and have concluded protocols to their CSAs which hold in abeyance many procedures in Part II of a CSA. These protocols are referred to as 'small quantities protocols' or 'SQPs' and remain in effect as long as the State meets certain eligibility criteria. The purpose of an SQP is to reduce the burden of safeguards implementation for States with little or no nuclear activities, while retaining the integrity of the safeguards system. States with SQPs have very important obligations they must fulfil under their CSAs. In 1997, as part of the IAEA's efforts to strengthen its safeguards system, the Model Additional Protocol to the Agreement(s) between State(s) and the International Atomic Energy Agency for the Application of Safeguards was developed to provide the IAEA with broader access to information and locations, thus significantly increasing the IAEA's ability to provide assurance of the absence of undeclared nuclear material and activities in States. Many States with SQPs have

  1. Seismic qualification of the rotary relay for use in the Trojan and Diablo Canyon Auxiliary Safeguards Cabinets

    International Nuclear Information System (INIS)

    Riggio, M.D.; Jarecki, S.J.

    1977-10-01

    This report presents the results of the analysis performed for the seismic qualification of the rotary relay for use in the Trojan and Diablo Canyon Auxiliary Safeguards Cabinets. A finite element model of the cabinet was developed from seismic test results. This model was analytically subjected to a simulated 3D floor acceleration time history that enveloped, simultaneously, the Trojan and the June 1969 Diablo Canyon Safe Shutdown Earthquake requirements. The dynamic response of the cabinet at the mounting location of the rotary relays was determined. The calculated acceleration time histories were converted to response spectra and these response spectra were compared to the test response spectra successfully achieved during the rotary relay seismic qualification tests. It was found that the dynamic motion levels at the rotary relays, when mounted in the Trojan or Diablo Canyon Auxiliary Safeguards Cabinets, do not exceed the levels for which they were previously seismically qualified by tests. Consequently, the rotary relays are seismically qualified for use in the Trojan or Diablo Canyon Auxiliary Safeguards Cabinets

  2. Nuclear safeguards technology 1986

    International Nuclear Information System (INIS)

    1987-01-01

    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

  3. IAEA safeguards: Stemming the spread of nuclear weapons. As the world's nuclear inspectorate, the IAEA performs an indispensable role in furthering nuclear non-proliferation

    International Nuclear Information System (INIS)

    2002-01-01

    Following the completion of the Treaty on the Non- Proliferation of Nuclear Weapons (NPT) in 1968, the IAEA has become the instrument with which to verify that the peaceful use commitments made under the NPT or similar agreements are kept through performing what is known as its safeguards role. Under the NPT, governments around the world have committed to three common objectives: preventing the proliferation of nuclear weapons; pursuing nuclear disarmament; and promoting the peaceful uses of nuclear energy. The NPT has made it obligatory for all its non-nuclear weapon State parties to submit all nuclear material in nuclear activities to IAEA safeguards, and to conclude a comprehensive safeguards agreement with the Agency. With all but a handful of the world community as State parties, the NPT is by far the most widely adhered to legal agreement in the field of disarmament and non-proliferation. The IAEA takes account of all source and special fissionable material in countries under safeguards. Monitoring and verification activities focus on those types of nuclear material that are the most crucial and relevant to nuclear weapons manufacturing. This includes plutonium-239, uranium-233 and -235 and any material containing one or more of these. Safeguards activities are applied routinely at over 900 facilities in 71 countries. In 2001 alone, more than 21,000 calendar days in the field were devoted to verifying hundreds of tons of special fissionable material by more than IAEA 250 inspectors

  4. IAEA symposium on international safeguards. Extended synopses

    International Nuclear Information System (INIS)

    1997-10-01

    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

  5. Verifying compliance with nuclear non-proliferation undertakings: IAEA safeguards agreements and additional protocols

    International Nuclear Information System (INIS)

    2008-06-01

    This report provides background information on safeguards and explains procedures for States to conclude Additional Protocols to comprehensive Safeguards Agreements with the IAEA. Since the IAEA was founded in 1957, its safeguards system has been an indispensable component of the nuclear non-proliferation regime and has facilitated peaceful nuclear cooperation. In recognition of this, the Treaty on the Non-Proliferation of Nuclear Weapons (NPT) makes it mandatory for all non-nuclear-weapon States (NNWS) party to the Treaty to conclude comprehensive safeguards agreements with the IAEA, and thus allow for the application of safeguards to all their nuclear material. Under Article III of the NPT, all NNWS undertake to accept safeguards, as set forth in agreements to be negotiated and concluded with the IAEA, for the exclusive purpose of verification of the fulfilment of the States' obligations under the NPT. In May 1997, the IAEA Board of Governors approved the Model Additional Protocol to Safeguards Agreements (reproduced in INFCIRC/540(Corr.)) which provided for an additional legal authority. In States that have both a comprehensive safeguards agreement and an additional protocol in force, the IAEA is able to optimize the implementation of all safeguards measures available. In order to simplify certain procedures under comprehensive safeguards agreements for States with little or no nuclear material and no nuclear material in a facility, the IAEA began making available, in 1971, a 'small quantities protocol' (SQP), which held in abeyance the implementation of most of the detailed provisions of comprehensive safeguards agreements for so long as the State concerned satisfied these criteria. The safeguards system aims at detecting and deterring the diversion of nuclear material. Such material includes enriched uranium, plutonium and uranium-233, which could be used directly in nuclear weapons. It also includes natural uranium and depleted uranium, the latter of which is

  6. Verifying compliance with nuclear non-proliferation undertakings: IAEA safeguards agreements and additional protocols

    International Nuclear Information System (INIS)

    2008-04-01

    This report provides background information on safeguards and explains procedures for States to conclude Additional Protocols to comprehensive Safeguards Agreements with the IAEA. Since the IAEA was founded in 1957, its safeguards system has been an indispensable component of the nuclear non-proliferation regime and has facilitated peaceful nuclear cooperation. In recognition of this, the Treaty on the Non-Proliferation of Nuclear Weapons (NPT) makes it mandatory for all non-nuclear-weapon States (NNWS) party to the Treaty to conclude comprehensive safeguards agreements with the IAEA, and thus allow for the application of safeguards to all their nuclear material. Under Article III of the NPT, all NNWS undertake to accept safeguards, as set forth in agreements to be negotiated and concluded with the IAEA, for the exclusive purpose of verification of the fulfilment of the States' obligations under the NPT. In May 1997, the IAEA Board of Governors approved the Model Additional Protocol to Safeguards Agreements (reproduced in INFCIRC/540(Corr.)) which provided for an additional legal authority. In States that have both a comprehensive safeguards agreement and an additional protocol in force, the IAEA is able to optimize the implementation of all safeguards measures available. In order to simplify certain procedures under comprehensive safeguards agreements for States with little or no nuclear material and no nuclear material in a facility, the IAEA began making available, in 1971, a 'small quantities protocol' (SQP), which held in abeyance the implementation of most of the detailed provisions of comprehensive safeguards agreements for so long as the State concerned satisfied these criteria. The safeguards system aims at detecting and deterring the diversion of nuclear material. Such material includes enriched uranium, plutonium and uranium-233, which could be used directly in nuclear weapons. It also includes natural uranium and depleted uranium, the latter of which is

  7. Safeguards Guidance Document for Designers of Commercial Nuclear Facilities: International Nuclear Safeguards Requirements and Practices For Uranium Enrichment Plants

    Energy Technology Data Exchange (ETDEWEB)

    Robert Bean; Casey Durst

    2009-10-01

    This report is the second in a series of guidelines on international safeguards requirements and practices, prepared expressly for the designers of nuclear facilities. The first document in this series is the description of generic international nuclear safeguards requirements pertaining to all types of facilities. These requirements should be understood and considered at the earliest stages of facility design as part of a new process called “Safeguards-by-Design.” This will help eliminate the costly retrofit of facilities that has occurred in the past to accommodate nuclear safeguards verification activities. The following summarizes the requirements for international nuclear safeguards implementation at enrichment plants, prepared under the Safeguards by Design project, and funded by the U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA), Office of NA-243. The purpose of this is to provide designers of nuclear facilities around the world with a simplified set of design requirements and the most common practices for meeting them. The foundation for these requirements is the international safeguards agreement between the country and the International Atomic Energy Agency (IAEA), pursuant to the Treaty on the Non-proliferation of Nuclear Weapons (NPT). Relevant safeguards requirements are also cited from the Safeguards Criteria for inspecting enrichment plants, found in the IAEA Safeguards Manual, Part SMC-8. IAEA definitions and terms are based on the IAEA Safeguards Glossary, published in 2002. The most current specification for safeguards measurement accuracy is found in the IAEA document STR-327, “International Target Values 2000 for Measurement Uncertainties in Safeguarding Nuclear Materials,” published in 2001. For this guide to be easier for the designer to use, the requirements have been restated in plainer language per expert interpretation using the source documents noted. The safeguards agreement is fundamentally a

  8. NPT safeguards and the peaceful use of nuclear energy

    International Nuclear Information System (INIS)

    Kyd, D.R.

    1993-10-01

    Origin of safeguards system and of comprehensive safeguards agreements, assurance given by IAEA safeguards, penalties and sanctions in case of breach of a safeguards agreement, recent experiences with Iraq, South Africa and DPRK as well as limits of the safeguards system are described

  9. IAEA safeguards: Challenges and opportunities

    International Nuclear Information System (INIS)

    1993-01-01

    The history of the IAEA safeguards regime is described. New challenges and opportunities are discussed in connection with the discovery in Iraq of a clandestine nuclear weapons development programme, the difficulties experienced in the implementation of the safeguards agreement with the Democratic People's Republic of Korea, the conclusion of a comprehensive safeguards agreement with Argentina, Brazil and the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials, recent developments in South Africa, the emergence of newly independent States that made up the former USSR. 2 figs

  10. Integrated safeguards and facility design and operations

    International Nuclear Information System (INIS)

    Tape, J.W.; Coulter, C.A.; Markin, J.T.; Thomas, K.E.

    1987-01-01

    The integration of safeguards functions to deter or detect unauthorized actions by an insider requires the careful communication and management of safeguards-relevant information on a timely basis. The traditional separation of safeguards functions into physical protection, materials control, and materials accounting often inhibits important information flows. Redefining the major safeguards functions as authorization, enforcement, and verification, and careful attention to management of information from acquisition to organization, to analysis, to decision making can result in effective safeguards integration. The careful inclusion of these ideas in facility designs and operations will lead to cost-effective safeguards systems. The safeguards authorization function defines, for example, personnel access requirements, processing activities, and materials movements/locations that are permitted to accomplish the mission of the facility. Minimizing the number of authorized personnel, limiting the processing flexibility, and maintaining up-to-date flow sheets will facilitate the detection of unauthorized activities. Enforcement of the authorized activities can be achieved in part through the use of barriers, access control systems, process sensors, and health and safety information. Consideration of safeguards requirements during facility design can improve the enforcement function. Verification includes the familiar materials accounting activities as well as auditing and testing of the other functions

  11. Implementation of integrated safeguards in Nuclear Fuel Plant at Pitesti, Romania

    International Nuclear Information System (INIS)

    Olaru, V.; Ivana, T.; Epure, Gh.

    2009-01-01

    The nuclear activity was conducted for many years in Romania under Traditional Safeguards (TS) and has developed in good conditions the specific nuclear safeguards. Now there is a good opportunity to improve the performance and quality of the safeguards activity and at the same time to increase the accountancy and control of nuclear materials by passing to Integrated Safeguards (IS) implementation. The legal framework is the Law 100/2000 for ratification of the Protocol between Romania and International Atomic Energy Agency (IAEA), additional completion to the Agreement between the Socialist Republic of Romania Government and IAEA relating to safeguards. It is 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 published in the Official Gazette no. 295/ 29.06.2000. The first discussion about Integrated Safeguards (IS) between the Nuclear Fuel Plant (FCN) representatives and IAEA inspectors has taken place in June 2005. In Feb. 2007 an IAEA mission visited FCN and established the main steps for implementing the IS. There were visited the storage and the technological flow and it was reviewed the residence times for different nuclear materials, the applied chemical analysis, metrological methods, weighting method and procedures of elaborating the implied documents and lists. At the same time the IAEA and FCN representatives established the main points for implementing the IS at FCN i.e. performing the Short Notice Random Inspections (SNRI), communicating the eligible days for SNRI for each year, communicating the estimated deliveries and shipments for the first quarter and then for the rest of the year, mail box daily declaration (DD) with respect to the residence time for several nuclear materials, advance notification (AN) for each nuclear material transfer (shipments and receipts), etc. At 01 June 2007 Romania has passed officially to Integrated Safeguards and FCN (RO

  12. 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.

  13. Inspection technologies -Development of national safeguards technology-

    International Nuclear Information System (INIS)

    Hong, J. S.; Kim, B. K.; Kwack, E. H.

    1996-12-01

    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. IAEA symposium on international safeguards. Extended synopses

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-10-01

    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 Refs, figs, tabs

  15. Tokai Advanced Safeguards Technology Exercise (TASTEX). An experience in international co-operation on safeguards

    International Nuclear Information System (INIS)

    Fukuda, G.; Koizumi, T.; Higuchi, K.

    1983-01-01

    TASTEX stands for Tokai Advanced Safeguards Technology Exercise, and was the joint programme of Japan, the United States of America, France and the International Atomic Energy Agency for developing, testing and evaluating advanced safeguards technology to be used in reprocessing facilities. The TASTEX programme, which started early in 1978 and successfully ended in May 1981, consisted of thirteen safeguards-technology-related tasks, from Task A to M. They were classified into four groups from the viewpoints of their usefulness and effectiveness: (1) Tasks technically feasible for international safeguards application in the near future: Tasks E, G, H and part of Task A (underwater CCTV and monitoring cameras); (2) Tasks which can be used in the future if research and development are continued: Tasks F, I, J, C and the other part of Task A (exclusive of the themes shown in (1)); (3) Tasks which may be used in future at the Tokai Reprocessing Facility if research and development are continued: Tasks K and L; and (4) Tasks which are difficult to be used at the Tokai Reprocessing Facility: Tasks B, D and M. The tasks classified under Group (1) are being developed further as part of the JASPAS (Japan Support Programme for Agency's Safeguards) project. (author)

  16. Safeguards and Physics Measurements: Services

    International Nuclear Information System (INIS)

    Carchon, R.

    2000-01-01

    SCK-CEN's department of Safeguards and Physics Measurements provides a wide variety of internal and external services including dosimetry, calibration, instrumentation, whole body counting, safeguards and non-destructive analysis. Main developments in these areas in 1999 are described

  17. 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.

  18. Future issues in international safeguards

    International Nuclear Information System (INIS)

    Hakkila, E.A.; Markin, J.T.; Mullen, M.F.

    1991-01-01

    The introduction of large bulk-handling facilities into the internationally safeguarded, commercial nuclear fuel cycle, increased concerns for radiation exposure, and the constant level of resources available to the International Atomic Energy Agency (IAEA) are driving new and innovative approaches to international safeguards. Inspector resources have traditionally been allocated on a facility-type basis. Approaches such as randomization of inspections either within a facility or across facilities in a State or the application of a fuel-cycle approach within a State are being considered as means of conserving resources. Large bulk-handling facilities require frequent material balance closures to meet IAEA timeliness goals. Approaches such as near-real-time accounting, running book inventories, and adjusted running book inventories are considered as means to meet these goals. The automated facilities require that safeguards measures also be automated, leading to more reliance on operator-supplied equipment that must be authenticated by the inspectorate. New Non-Proliferation Treaty signatory States with advanced nuclear programs will further drain IAEA resources. Finally, the role of special inspections in IAEA safeguards may be expanded. This paper discusses these issues in terms of increasing safeguards effectiveness and the possible impact on operators. 14 refs

  19. Strengthened safeguards: Present and future challenges

    International Nuclear Information System (INIS)

    Goldschmidt, Pierre

    2001-01-01

    Full text: The safeguards system is experiencing what has been seen as a revolution and, in doing so, it is confronting a series of challenges. These can be grouped into three areas. Drawing and maintaining safeguards conclusions - The process by which the safeguards conclusions are derived is based upon the analysis, evaluation and review of all the information available to the Agency. This process is on- going, but the State Evaluation Reports are compiled and reviewed periodically. For States with an additional protocol in force, the absence of indicators of the presence of undeclared nuclear material or activities provides the basis for the safeguards conclusion. Future challenges center on States' expectations of, and reactions to, the results of the evaluation and review process. Designing and implementing integrated safeguards - The conceptual framework of integrated safeguards is being actively pursued. Basic principles have been defined and integrated safeguards approaches have been developed for various types of facilities. Work is also progressing on the design of integrated safeguards approaches for specific States. Complementary access is being successfully implemented, and procedures for the use of unannounced inspections are being developed with the prospect of cost- effectiveness gains. Costs neutrality vs. quality and credibility - The Department faces serious staff and financial challenges. It has succeeded so far in 'doing more' and 'doing better' within a zero-real growth budget, but the scope for further significant efficiency gains is exhausted. There is no capacity to absorb new or unexpected tasks. Difficulties in recruiting and retaining qualified and experienced staff exacerbate the problems and add to costs. The Director General of the IAEA has referred to the need for new initiatives to bridge the budgetary gap; a possible measure is proposed. The tasks of meeting the challenges and demands of strengthened safeguards have been added to

  20. IMPACT OF THE U.S. SUPPORT PROGRAM SAFEGUARDS INTERNSHIP PROGRAM

    International Nuclear Information System (INIS)

    PEPPER, S.; OSIECKI, C.

    2006-01-01

    The U.S. Support Program began funding an internship program in the IAEA Department of Safeguards in 2002. Since that time, 39 U.S. citizens and permanent residents have been placed in one-year, paid internships with the IAEA. The management of the internship program was originally the responsibility of the International Safeguards Project Office but was transferred to the Office of Educational Programs at Brookhaven National Laboratory in 2004. Feedback on the internship program from the U.S. government and the IAEA has been positive. The interns have completed basic yet essential work for the Department of Safeguards and freed IAEA staff members to perform more complex tasks. The cost of an intern is low relative to other forms of human resources support. After the conclusion of their assignments, many of the interns go on to work for the U.S. government, the national laboratories, or companies in international safeguards and nonproliferation. This paper will discuss the work done by the interns for the IAEA, factors influencing the success of the internship program, and the effects the program has had on the careers of interns, in preparing the next generation to work in the nuclear industry, participation in INMM activities, and recruitment for U.S. citizens for safeguards positions

  1. 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.

  2. Safeguards culture on 3S interfaces

    International Nuclear Information System (INIS)

    Jeong, Yon Hong; Lee, Na Young; Han, Jae-Jun

    2015-01-01

    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

  3. A Little Customs Glossary for IAEA Safeguards: Customs Procedures and Concepts that Matter for the Implementation of Modern Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Chatelus, Renaud [Consultant, Export Control and IAEA Safeguards Specialist, IAEA (International Atomic Energy Agency (IAEA))

    2012-06-15

    The additional protocols to the IAEA comprehensive safeguards agreements include provisions about the reporting by states of their imports and exports of listed equipment and non-nuclear material, also known as the 'trigger list', as well as nuclear materials. Beyond declarations and their verification, IAEA Safeguards also looks at other Imports and exports as part of its efforts to build confidence on the absence of undeclared nuclear activities or material. In all cases, information about international transfers of interest to Nuclear Safeguards is closely related to export control activities. But, if much has been written about the material and equipment to be declared, neither IAEA Safeguards nor Export control related documents provide much explanation about what exports and imports actually are. In fact, precise legal definitions are to be found generally in national customs regulations and international agreements on customs and trade. Unfortunately, these are not necessarily in line with Safeguards understanding. It is therefore essential that IAEA safeguards comprehends the customs concepts and procedures that are behind Safeguards relevant information.

  4. A Little Customs Glossary for IAEA Safeguards: Customs Procedures and Concepts that Matter for the Implementation of Modern Safeguards

    International Nuclear Information System (INIS)

    Chatelus, Renaud; )

    2012-01-01

    The additional protocols to the IAEA comprehensive safeguards agreements include provisions about the reporting by states of their imports and exports of listed equipment and non-nuclear material, also known as the “trigger list”, as well as nuclear materials. Beyond declarations and their verification, IAEA Safeguards also looks at other Imports and exports as part of its efforts to build confidence on the absence of undeclared nuclear activities or material. In all cases, information about international transfers of interest to Nuclear Safeguards is closely related to export control activities. But, if much has been written about the material and equipment to be declared, neither IAEA Safeguards nor Export control related documents provide much explanation about what exports and imports actually are. In fact, precise legal definitions are to be found generally in national customs regulations and international agreements on customs and trade. Unfortunately, these are not necessarily in line with Safeguards understanding. It is therefore essential that IAEA safeguards comprehends the customs concepts and procedures that are behind Safeguards relevant information.

  5. 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.

  6. Safeguards summary event list (SSEL)

    International Nuclear Information System (INIS)

    1989-07-01

    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

  7. Safeguards Summary Event List (SSEL)

    International Nuclear Information System (INIS)

    Fadden, M.; Yardumian, J.

    1993-07-01

    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

  8. Potential development of non-destructive assay for nuclear safeguards

    International Nuclear Information System (INIS)

    Benoit, R.; Cuypers, M.; Guardini, S.

    1983-01-01

    After a brief summary on the role of non-destructive assay in safeguarding the nuclear fuel cycle, its evolution from NDA methods development to other areas is illustrated. These areas are essentially: a) the evaluation of the performances of NDA techniques in field conditions; b) introduction of full automation of measurement instrument operation, using interactive microprocessors and of measurement data handling evaluation and retrieval features; c) introduction of the adequate link and compatibility to assure NDA measurement data transfer in an integrated safeguards data evaluation scheme. In this field, the Joint Research Centre (JRC) of the Commission of the European Communities (CEC) is developing and implementing a number of techniques and methodologies allowing an integrated and rational treatment of the large amount of safeguards data produced. In particular for the non-destructive assay measurements and techniques, the JRC has studied and tested methodologies for the automatic generation and validation of data of inventory verification. In order to apply these techniques successfully in field, the JRC has studied the design requirements of NDA data management and evaluation systems. This paper also discusses the functional requirements of an integrated system for NDA safeguards data evaluation

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

    International Nuclear Information System (INIS)

    Tape, James W.

    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.

  10. Key Nuclear Verification Priorities: Safeguards and Beyond

    International Nuclear Information System (INIS)

    Carlson, J.

    2010-01-01

    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

  11. Key Nuclear Verification Priorities - Safeguards and Beyond

    International Nuclear Information System (INIS)

    Carlson, J.

    2010-01-01

    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

  12. IAEA's Safeguards Implementation Practices Guides

    International Nuclear Information System (INIS)

    Mathews, C.; Sahar, S.; Cisar, V.

    2015-01-01

    Implementation of IAEA safeguards benefits greatly from effective cooperation among the IAEA, State or regional authorities (SRAs), and operators of facilities and other locations. To improve such cooperation, the IAEA has produced numerous safeguards guidance documents in its Services Series publications. The IAEA also provides assistance, training and advisory services that are based on the published guidance. The foundation of the IAEA's safeguards guidance is the Guidance for States Implementing Comprehensive Safeguards Agreements and Additional Protocols (IAEA Services Series 21) published in March of 2012. The large majority of States have concluded CSAs and therefore will benefit from this guidance. Many States with CSAs also have concluded small quantities protocols (SQPs) to their CSAs. In April of 2013, the IAEA published the Safeguards Implementation Guide for States with SQPs (IAEA Services Series 22). Other guidance focuses on specific topics such as preparing additional protocol declarations and nuclear material accounting. This paper will describe a recent effort to produce a ''Safeguards Implementation Practices'' (SIP) series of guides that will provide additional explanatory information about safeguards implementation, and share the practical experiences and lessons learned of States and the IAEA over the many decades of implementing safeguards. The topics to be addressed in four SIP guides include: 1) Facilitating IAEA Verification Activities; 2) Establishing and Maintaining State Safeguards Infrastructure; 3) Provision of Information to the IAEA; and 4) Collaborative Approaches to Safeguards Implementation. The SIP Guides build upon the content of IAEA Services Series 21. Because the SIP Guides are intended to share implementation practices and lessons learned of States, a number of experienced State experts have participated in the development of the documents, through a joint Member State Support Programme task

  13. A Priority-Based View of Future Challenges in International Nuclear Safeguards.

    Energy Technology Data Exchange (ETDEWEB)

    Matteucci, Kayla [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-06-01

    The international nuclear safeguards community is faced with a host of challenges in the coming years, many of which have been outlined but have not been described in terms of their urgency. Literature regarding safeguards challenges is either broad and devoid of any reference to prioritization or tailored to a specific problem and removed from the overall goals of the safeguards community. For example, developing new methods of environmental sampling, improving containment and surveillance (C/S) technologies to increase efficiency and decrease inspection time, advancing nuclear material accountancy (NMA) techniques, and planning safeguards approaches for new types of nuclear facilities are all important. They have not, however, been distinctly prioritized at a high level within the safeguards community. Based on a review of existing literature and interviews with experts on these upcoming challenges, this paper offers a high-level summary of present and future priorities in safeguards, with attention both to what is feasible and to what is most imperative. In doing so, the paper addresses the potential repercussions for failing to prioritize, with a focus on the risk of diversion of nuclear material. Within the context of shifts in the American political landscape, and keeping in mind that nonproliferation issues may take a backseat to others in the near future, a prioritized view of safeguards objectives will be vital. In the interest of expanding upon this work, the paper offers several potential conceptual models for prioritization which can be explored in greater depth upon further research.

  14. 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.

  15. Analysis on the status of the application of satellite remote sensing technology to nuclear safeguards

    International Nuclear Information System (INIS)

    Tao Zhangsheng; Zhao Yingjun

    2008-01-01

    Based on the application status of satellite remote sensing technology to nuclear safeguards, advantage of satellite remote sensing technology is analyzed, main types of satellite image used in nuclear safeguards are elaborated and the main application of satellite images is regarded to detect, verify and monitor nuclear activities; verify additional protocol declaration and design information, support performing complementary access inspections; investigate alleged undeclared activities based on open source or the third party information. Application examples of satellite image in nuclear safeguards to analyze nuclear facilities by other countries, the ability of remote sensing technology in nuclear safeguards is discussed. (authors)

  16. Video image processing for nuclear safeguards

    International Nuclear Information System (INIS)

    Rodriguez, C.A.; Howell, J.A.; Menlove, H.O.; Brislawn, C.M.; Bradley, J.N.; Chare, P.; Gorten, J.

    1995-01-01

    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

  17. Safeguards Automated Facility Evaluation (SAFE) methodology

    International Nuclear Information System (INIS)

    Chapman, L.D.; Grady, L.M.; Bennett, H.A.; Sasser, D.W.; Engi, D.

    1978-08-01

    An automated approach to facility safeguards effectiveness evaluation has been developed. This automated process, called Safeguards Automated Facility Evaluation (SAFE), consists of a collection of a continuous stream of operational modules for facility characterization, the selection of critical paths, and the evaluation of safeguards effectiveness along these paths. The technique has been implemented on an interactive computer time-sharing system and makes use of computer graphics for the processing and presentation of information. Using this technique, a comprehensive evaluation of a safeguards system can be provided by systematically varying the parameters that characterize the physical protection components of a facility to reflect the perceived adversary attributes and strategy, environmental conditions, and site operational conditions. The SAFE procedure has broad applications in the nuclear facility safeguards field as well as in the security field in general. Any fixed facility containing valuable materials or components to be protected from theft or sabotage could be analyzed using this same automated evaluation technique

  18. NNSA's next generation safeguards initiative to define an effective state system of accounting and control

    International Nuclear Information System (INIS)

    Stevens, Rebecca S.; Sunshine, Alexander; Matthews, Caroline; Frazer, Sarah; Matthews, Carrie

    2010-01-01

    build confidence in the State System. Viewed from this perspective, the model can be thought of as a quality assurance tool that assists states in ensuring that the outputs of their State System (the tangible 'goods' that are provided to the International Atomic Energy Agency under the State's agreements) are of high quality. As such, this tool is for the internal use of a State System that wishes to assess and improve its capacity. It is not intended for comparison or outside evaluation. In addition to providing a self-assessment tool, INSEP expects this model to be useful in several other ways: it will inform the approach that INSEP uses in bilateral consultations to identify areas where INSEP outreach and training may be of value, and it will provide a structure for its training curriculum. It will help INSEP to evaluate the effectiveness of its outreach - where there are gaps in the training provided, and whether the training that is provided meets its stated objectives. Finally, it will provide a framework for coordinating with the IAEA and other member states in the 'harmonization' efforts currently underway to align the outreach efforts of states that provide safeguards training. This paper describes the process of evaluation that INSEP is developing. It looks at the expected usefulness of the metrics for conducting self-assessments and joint assessments and enabling partners to identify training needs. The paper begins with a description of various performance requirements that define what must be done at the state and facility level to implement effective and efficient international safeguards. Next, technical performance measures are discussed, that define how well a state and its facilities are fulfilling these requirements. Then a functional analysis is conducted to align the technical requirements with competencies and determine who should carry out the various activities necessary to fulfill the performance requirements. Finally, the paper concludes with a

  19. A Legal Analysis of Safeguard Measures in the European Community

    Directory of Open Access Journals (Sweden)

    Guang Ma

    2006-12-01

    Full Text Available In 2002, the European Community imposed its first safeguard measure since the establishment of the WTO. And in 2003, it introduced two new regulations on safeguard measures, namely the “Council Regulation on a transitional product- specific safeguard mechanism for imports originating in the People's Republic of China” and the “Council Regulation on measures that the Community may take in relation to the combined effect of anti-dumping or anti-subsidy measures with safeguard measures." In this article, the author analyzes these safeguard measures and the European Commission's practice of such measures. By comparing the safeguard laws and their practice, it is the author's intention to clarify whether the safeguard measures in thIn 2002, the European Community imposed its first safeguard measure since the establishment of the WTO. And in 2003, it introduced two new regulations on safeguard measures, namely the "Council Regulation on a transitional product- specific safeguard mechanism for imports originating in the People's Republic of China" and the "Council Regulation on measures that the Community may take in relation to the combined effect of anti-dumping or anti-subsidy measures with safeguard measures." In this article, the author analyzes these safeguard measures and the European Commission's practice of such measures. By comparing the safeguard laws and their practice, it is the author's intention to clarify whether the safeguard measures in the European Community comply with the WTO Agreement on Safeguards. In conclusion, based on the analysis of safeguard measures in the European Community's legal system and their practice in actual cases, it apparent that the European Community is making a serious effort to comply with the standards of the WTO Safeguards Agreement. In certain respects, the European Community has a comparatively higher level of standards than the WTO. Nevertheless, there continue to be challenges to WTO

  20. Guarantying and testing the nuclear safeguards

    International Nuclear Information System (INIS)

    Turcu, Ilie

    2002-01-01

    Apparently, the nuclear power will ensure an important share of the world energy demand at least for the next decades because there is no viable alternative in the fan of energy sources neither one complying with the environment preservation requirements. The nuclear energy future depends not only on technical and economical aspects but also on preventing any danger of nuclear safeguards nature. The main international legal instrument which provides concrete commitments for nations in this field is the Nuclear Safeguard Convention. It provides guarantees and testings of the nuclear safeguards over the entire service life of the nuclear power plants. In the two general conferences (of 1999 and 2002) the status and measures adopted in the field of nuclear safeguards by the states adhering to the convention were discussed and reviewed, as well as the issues of financial resources, licensing and the adequate measures in emergency cases. The nuclear safeguards is a major issue among the criteria of integration in UE. Essential for maintaining and endorsing the provisions of nuclear safeguards in Romania are specific research and development activities aiming at integrating the equipment and structures, solving the operation problems of nuclear facilities, studying the behavior of installations in transient regimes, investigating the reliability and probabilistic assessing of nuclear safeguards, examining the phenomenology and simulating severe accidents or human factor behavior. Of major importance appears to be the international cooperation aiming that a permanent exchange of information and experience, dissemination of the best results, solutions and practices. The paper presents the status and trends at the world level, as well as in Romania, underlining the main issues of the strategy in this field and stressing the financial and human resources implied the implementing the nuclear safeguards provisions

  1. Towards more efficient safeguards approach of transfer campaign in Wolsong CANDU reactor

    International Nuclear Information System (INIS)

    Park, S. K.; Na, W. W.; Park, W. S.; Jung, S. T.; Park, S. J.

    2002-01-01

    Due to the unique character of the CANDU reactor, a transfer campaign has been carried out every year for 2 months or so in Wolsong unit 1. It is expected to require performance of the transfer campaign for 4 units of Wolsong site in 2006 and more than 50% of the ROK safeguards inspection efforts. The IAEA and TCNC have gained several years of experience in safeguards approach during transfer campaign. Occasionally the deterrence and interference of operator transfer work have been occurred in order to attain safeguards inspection goal. These could be minimized using optimum C/S applications, NDA and RDT techniques. This paper shows the interrelationship and combinations of these resources and proposes new safeguards approach to maintain the continuity of knowledge from fuel loading in the spent fuel pond to the point of canister loading and closure during transfer campaign

  2. Advanced integrated safeguards at Barnwell

    International Nuclear Information System (INIS)

    Bambas, K.J.; Barnes, L.D.

    1980-06-01

    The development and initial performance testing of an advanced integrated safeguards system at the Barnwell Nuclear Fuel Plant (BNFP) is described. The program concentrates on the integration and coordination of physical security and nuclear materials control and accounting at a single location. Hardware and software for this phase have been installed and are currently being evaluated. The AGNS/DOE program is now in its third year of development at the BNFP

  3. Nuclear safety, security and safeguards. An application of an integrated approach

    Energy Technology Data Exchange (ETDEWEB)

    Chapman, Howard; Edwards, Jeremy; Fitzpatrick, Joshua; Grundy, Colette; Rodger, Robert; Scott, Jonathan [National Nuclear Laboratory, Warrington (United Kingdom)

    2018-01-15

    National Nuclear Laboratory has recently produced a paper regarding the integrated approach of nuclear safety, security and safeguards. The paper considered the international acknowledgement of the inter-relationships and potential benefits to be gained through improved integration of the nuclear '3S'; Safety, Security and Safeguards. It considered that combining capabilities into one synergistic team can provide improved performance and value. This approach to integration has been adopted, and benefits realised by the National Nuclear Laboratory through creation of a Safety, Security and Safeguards team. In some instances the interface is clear and established, as is the case between safety and security in the areas of Vital Area Identification. In others the interface is developing such as the utilisation of safeguards related techniques such as nuclear material accountancy and control to enhance the security of materials. This paper looks at a practical example of the progress to date in implementing Triple S by a duty holder.

  4. Safeguards Implementation Practices Guide on Provision of Information to the IAEA

    International Nuclear Information System (INIS)

    2016-01-01

    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 Guide provides information which States may find useful in implementing their safeguards agreements with the IAEA

  5. Next Generation Safeguards Initiative: Human Capital Development

    International Nuclear Information System (INIS)

    Scholz, M.; Irola, G.; Glynn, K.

    2015-01-01

    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)

  6. Performance results from the first integrated NDA VXI safeguards system

    International Nuclear Information System (INIS)

    Bot, D.; Messner, R.

    1999-01-01

    The VIFM system is the first integrated safeguard system to be developed and deployed by the IAEA. The system is also noteworthy in that it is the most versatile of any NDA system thus far deployed. Due to the high level of functionality, the VIFM is probably the most 'tested' of all IAEA systems. This paper discusses the results obtained from detailed in field and laboratory testing of a variety of VIFM configurations ranging from simple single systems to highly integrated system implementations. A total of 4 sites have had VIFM equipment installed. Data collected from these sites have been of very high quality and consistency despite the failure of commercial hard disk drive equipment. The systematic failure of these drives have been corrected using a variety of methods and performance since those corrections have been excellent with no equipment failures. The tests carried out also included the test of a twisted pair to coaxial cable interface. This interface was required in order to allow installation even with a significant facility cabling limitation. The performance obtained from the system utilizing this device showed no degradation as compared to that of systems utilizing direct coaxial cable connections. To conclude, the VIFM system, has been reliable even after partial failure of commercial off-the-shelf components which required the systems to operate on full fail-safe backup. These tests have thus shown both the reliable operation of the VIFM in normal operating conditions as well as the most adverse

  7. Coordinated safeguards for materials management in a fuel reprocessing plant. Volume I

    International Nuclear Information System (INIS)

    Hakkila, E.A.; Cobb, D.D.; Dayem, H.A.; Dietz, R.J.; Kern, E.A.; Schelonka, E.P.; Shipley, J.P.; Smith, D.B.; Augustson, R.H.; Barnes, J.W.

    1977-09-01

    A materials management system is described for safeguarding special nuclear materials in a fuel-reprocessing plant. Recently developed nondestructive-analysis techniques and process-monitoring devices are combined with conventional chemical analyses and process-control instrumentation for improved materials accounting data. Unit-process accounting based on dynamic material balances permits localization of diversion in time and space, and the application of advanced statistical methods supported by decision-analysis theory ensures optimum use of accounting information for detecting diversion. This coordinated safeguards system provides maximum effectiveness consistent with modest cost and minimum process interference. Modeling and simulation techniques are used to evaluate the sensitivity of the system to single and multiple thefts and to compare various safeguards options. The study identifies design criteria that would improve the safeguardability of future plants

  8. Educating the next generation of nuclear safeguards and security experts at TAMU

    International Nuclear Information System (INIS)

    Charlton, William S.; Boyle, David; Chirayath, Sunil; Ford, David G.; Gariazzo, Claudio A.; Marianno, Craig; Ragusa, Kelley; Solodov, Alexander

    2011-01-01

    The Nuclear Security Science and Policy Institute (NSSPI) has established a Nuclear Nonproliferation specialization for the Master of Science degree within the Nuclear Engineering Department at Texas A and M University (TAMU). Since 2004, twenty-eight students have received MS degrees in this area and over 200 (technical and policy) students have taken classes offered by NSSPI at TAMU. The model for educating safeguards and security experts is being changed at TAMU. Beyond conventional classroom lectures, NSSPI has developed alternative educational models based on practical experience, asynchronous learning portals, and virtual courses in both nuclear safeguards and nuclear security. Due to the experimental and practical past experiences of NSSPI staff and faculty, a heavy hands-on component has been implemented for TAMU nuclear engineering graduate students: hands-on education at Oak Ridge National Laboratory, visiting nuclear installations in other countries to discuss applied safeguards, and summer internships at several national laboratories. In an effort to disseminate basic nuclear education for professionals and students around the globe, NSSPI has developed a publically-available online resource that offers self-paced, independent course modules in basic safeguards and security education: the Nuclear Safeguards Education Portal. Another venture utilized by NSSPI is using a virtual TAMU campus to hold classes for students at a distance. NSSPI is building upon a successful academic program by embracing new educational means. This paper describes the current efforts NSSPI and TAMU have undertaken in strengthening the nuclear nonproliferation, safeguards and security human resource capacity domestically and internationally and the lessons learned from these efforts. (author)

  9. Operationalizing social safeguards in REDD+: actors, interests and ideas

    International Nuclear Information System (INIS)

    McDermott, Constance L.; Coad, Lauren; Helfgott, Ariella; Schroeder, Heike

    2012-01-01

    + will remain a boundary object if it transitions to a national-level, performance based system where the design and enforcement of safeguards competes directly with financial compensation for measurable emissions reductions.

  10. Safeguards and physics measurements

    International Nuclear Information System (INIS)

    Carchon, R.

    2002-01-01

    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'

  11. Australian nuclear safeguards

    International Nuclear Information System (INIS)

    Kerin, J.C.

    1988-01-01

    The Australian Government considers that allegations made by the West German magazine - Der Spiegel in its January and February 1988 editions, flow from a lack of understanding of the complexities of international trade in nuclear materials, confusion between internal and international flag swaps and failure to comprehend the equivalence principle used in nuclear materials accounting. The Ministerial statement briefly outlines these issues and concludes that there is no evidence that any material subject to Australia's bilateral safeguards agreement has been diverted from peaceful uses or that Australia's safeguard requirements have been breached

  12. IAEA safeguards and classified materials

    International Nuclear Information System (INIS)

    Pilat, J.F.; Eccleston, G.W.; Fearey, B.L.; Nicholas, N.J.; Tape, J.W.; Kratzer, M.

    1997-01-01

    The international community in the post-Cold War period has suggested that the International Atomic Energy Agency (IAEA) utilize its expertise in support of the arms control and disarmament process in unprecedented ways. The pledges of the US and Russian presidents to place excess defense materials, some of which are classified, under some type of international inspections raises the prospect of using IAEA safeguards approaches for monitoring classified materials. A traditional safeguards approach, based on nuclear material accountancy, would seem unavoidably to reveal classified information. However, further analysis of the IAEA's safeguards approaches is warranted in order to understand fully the scope and nature of any problems. The issues are complex and difficult, and it is expected that common technical understandings will be essential for their resolution. Accordingly, this paper examines and compares traditional safeguards item accounting of fuel at a nuclear power station (especially spent fuel) with the challenges presented by inspections of classified materials. This analysis is intended to delineate more clearly the problems as well as reveal possible approaches, techniques, and technologies that could allow the adaptation of safeguards to the unprecedented task of inspecting classified materials. It is also hoped that a discussion of these issues can advance ongoing political-technical debates on international inspections of excess classified materials

  13. The standing advisory group on safeguards implementation

    International Nuclear Information System (INIS)

    Jennekens, J.H.F.

    1982-09-01

    In 1975 the Director General of the IAEA called together ten persons from member states with nuclear programs at varying stages of development to form the Standing Advisory Group on Safeguards Implementation. The group was later expanded to twelve. The Director General asked the group to evaluate the technical objectives of Agency safeguards, assess the effectiveness and efficiency of specific safeguards operating methods in meeting these technical objectives, advise on techniques to be employed in safeguards operations, and recommend areas where further work 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

  14. Legal instruments related to the application of safeguards

    International Nuclear Information System (INIS)

    Rames, J.

    1999-01-01

    This presentation discusses the legal framework of IAEA Safeguards which consists of a number of elements, including agreements calling for verification of nonproliferation undertakings, basic safeguards documents (INFCIRC/66/Rev.2, INFCIRC/153 (Corr..), INFCIRC/540 (Corr.), INFCIRC/9/Rev.2, GC(V)/INF/39), the safeguards agreements themselves, along with the relevant protocols and subsidiary arrangements, and finally the decisions, interpretations and practices of the Boards of Governors. Major differences between the various types of IAEA safeguards agreements are outlined. Procedures involved in the initiation, negotiation, conclusion and amendment of safeguard agreements are described

  15. Investigation of novel spent fuel verification system for safeguard application

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Haneol; Yim, Man-Sung [KAIST, Daejeon (Korea, Republic of)

    2016-10-15

    Radioactive waste, especially spent fuel, is generated from the operation of nuclear power plants. The final stage of radioactive waste management is disposal which isolates radioactive waste from the accessible environment and allows it to decay. The safety, security, and safeguard of a spent fuel repository have to be evaluated before its operation. Many researchers have evaluated the safety of a repository. These researchers calculated dose to public after the repository is closed depending on their scenario. Because most spent fuel repositories are non-retrievable, research on security or safeguards of spent fuel repositories have to be performed. Design based security or safeguard have to be developed for future repository designs. This study summarizes the requirements of future spent fuel repositories especially safeguards, and suggests a novel system which meets the safeguard requirements. Applying safeguards to a spent fuel repository is becoming increasingly important. The future requirements for a spent fuel repository are suggested by several expert groups, such as ASTOR in IAEA. The requirements emphasizes surveillance and verification. The surveillance and verification of spent fuel is currently accomplished by using the Cerenkov radiation detector while spent fuel is being stored in a fuel pool. This research investigated an advanced spent fuel verification system using a system which converts spent fuel radiation into electricity. The system generates electricity while it is conveyed from a transportation cask to a disposal cask. The electricity conversion system was verified in a lab scale experiment using an 8.51GBq Cs-137 gamma source.

  16. Investigation of novel spent fuel verification system for safeguard application

    International Nuclear Information System (INIS)

    Lee, Haneol; Yim, Man-Sung

    2016-01-01

    Radioactive waste, especially spent fuel, is generated from the operation of nuclear power plants. The final stage of radioactive waste management is disposal which isolates radioactive waste from the accessible environment and allows it to decay. The safety, security, and safeguard of a spent fuel repository have to be evaluated before its operation. Many researchers have evaluated the safety of a repository. These researchers calculated dose to public after the repository is closed depending on their scenario. Because most spent fuel repositories are non-retrievable, research on security or safeguards of spent fuel repositories have to be performed. Design based security or safeguard have to be developed for future repository designs. This study summarizes the requirements of future spent fuel repositories especially safeguards, and suggests a novel system which meets the safeguard requirements. Applying safeguards to a spent fuel repository is becoming increasingly important. The future requirements for a spent fuel repository are suggested by several expert groups, such as ASTOR in IAEA. The requirements emphasizes surveillance and verification. The surveillance and verification of spent fuel is currently accomplished by using the Cerenkov radiation detector while spent fuel is being stored in a fuel pool. This research investigated an advanced spent fuel verification system using a system which converts spent fuel radiation into electricity. The system generates electricity while it is conveyed from a transportation cask to a disposal cask. The electricity conversion system was verified in a lab scale experiment using an 8.51GBq Cs-137 gamma source

  17. Reporting of safeguards events

    International Nuclear Information System (INIS)

    Dwyer, P.A.; Ervin, N.E.

    1988-02-01

    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

  18. 10 CFR 72.184 - Safeguards contingency plan.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Safeguards contingency plan. 72.184 Section 72.184 Energy... Protection § 72.184 Safeguards contingency plan. (a) The requirements of the licensee's safeguards contingency plan for responding to threats and radiological sabotage must be as defined in appendix C to part...

  19. Safeguards planning in a plant design process

    International Nuclear Information System (INIS)

    Heinrich, L.A.

    1977-01-01

    The safeguards efforts for the partitioning fuel cycle are considered. Included in the discussion are the organization of the safeguards study, the development of safeguards criteria, the expression of these criteria as requirements for facility design, and some preliminary details of the implementation of these requirements in facility and process layout

  20. 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 for...

  1. Knowledge Management in the IAEA Department of Safeguards

    International Nuclear Information System (INIS)

    Konecni, S.; Carrillo de Fischer, J.

    2016-01-01

    Full text: Knowledge Management (KM) is an integral part of the Departmental Quality Management System because knowledge (i.e., the ‘know-how’, ‘know-when’, ‘know-who’, ‘know-why’, etc.) is needed to produce high quality products and services on a daily basis. The ability to continue providing such products and services is challenged each time an experienced staff member leaves the IAEA due to retirement or end of contract and takes with them important job-related knowledge. The most important assets in the International Atomic Energy Agency (IAEA) Department of Safeguards (SG) are people and their knowledge. The Department of Safeguards developed a knowledge management (KM) framework and the corresponding approaches as well as specific guidelines for its implementation. Knowledge retention (KR) is part of knowledge management and focusses on eliminating the risk of losing the critical job-related knowledge by putting in place a systematic knowledge retention plan. Particularly, for knowledge retention, the Safeguards Division of Concepts and Planning (SGCP) developed a model to draw out and capture the critical knowledge and making it available for use by others. This paper describes the knowledge retention model/approach and lessons learned from implementing the knowledge management programme in SG. (author

  2. 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.

  3. Safeguards Envelope Progress FY08

    International Nuclear Information System (INIS)

    Bean, Robert; Metcalf, Richard; Bevill, Aaron

    2008-01-01

    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

  4. Leveraging physical protection technology for international safeguards applications

    International Nuclear Information System (INIS)

    Glidewell, Don

    2001-01-01

    Full text: In an effort to improve the effectiveness, efficiency, and reliability of equipment used for International Safeguards, the European Safeguards Research and Development Association (ESARDA) Reflection Group requested the ESARDA Containment and Surveillance Working Group to investigate the feasibility of employing physical protection technologies for international safeguards applications. The physical protection market has traditionally been much greater than the international safeguards market. Consequently, physical protection technology has been subjected to greater testing and evaluation, and has enjoyed much greater real world experience. The larger market yields economies of scale, and the greater testing and experience should arguably result in improved reliability. This paper will compare requirements for physical protection versus international safeguards equipment, and identify types of physical protection equipment, which have potential for safeguards applications. It will evaluate both Commercial Off-the-Shelf (COTS) and non-COTS equipment. Finally, for selected physical protection equipment, the paper will evaluate the degree of modification that would be needed to make it acceptable for safeguards applications. (author)

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

    International Nuclear Information System (INIS)

    Long, Jon D.; McGinnis, Brent R.; Morgan, James B.; Whitaker, Michael; Lockwood, Dunbar; Shipwash, Jacqueline L.

    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 Facilities Working

  6. Safeguarding and Protecting the Nuclear Fuel Cycle

    International Nuclear Information System (INIS)

    Bjornard, Trond; Garcia, Humberto; Desmond, William; Demuth, Scott

    2010-01-01

    International safeguards as applied by the International Atomic Energy Agency (IAEA) are a vital cornerstone of the global nuclear nonproliferation regime - they protect against the peaceful nuclear fuel cycle becoming the undetected vehicle for nuclear weapons proliferation by States. Likewise, domestic safeguards and nuclear security are essential to combating theft, sabotage, and nuclear terrorism by non-State actors. While current approaches to safeguarding and protecting the nuclear fuel cycle have been very successful, there is significant, active interest to further improve the efficiency and effectiveness of safeguards and security, particularly in light of the anticipated growth of nuclear energy and the increase in the global threat environment. This article will address two recent developments called Safeguards-by-Design and Security-by-Design, which are receiving increasing broad international attention and support. Expected benefits include facilities that are inherently more economical to effectively safeguard and protect. However, the technical measures of safeguards and security alone are not enough - they must continue to be broadly supported by dynamic and adaptive nonproliferation and security regimes. To this end, at the level of the global fuel cycle architecture, 'nonproliferation and security by design' remains a worthy objective that is also the subject of very active, international focus.

  7. International safeguards

    International Nuclear Information System (INIS)

    Petit, A.

    1991-01-01

    The IAEA has now 200 Inspectors or so, and Euratom a similar number. People in Vienna are talking about increases of this staff, in the range of a possible doubling in the five years to come, although even an immediate restart of the expansion of nuclear industry, would not materialize significantly within this period. This means that keeping the same safeguarding approach would probably lead to another doubling of such staff in the ten following years, which is completely unrealistic. Such a staff is our of proportion with those of national inspectorates in other fields. The paper analyzes the basic irrealistic dogma which have hindered the progress of international safeguards, and recall the suggestions made since ten years to improve them

  8. Accountability and non-proliferation nuclear regime: a review of the mutual surveillance Brazilian-Argentine model for nuclear safeguards; Accountability e regime de nao proliferacao nuclear: uma avaliacao do modelo de vigilancia mutua brasileiro-argentina de salvaguardas nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Xavier, Roberto Salles

    2014-08-01

    The regimes of accountability, the organizations of global governance and institutional arrangements of global governance of nuclear non-proliferation and of Mutual Vigilance Brazilian-Argentine of Nuclear Safeguards are the subject of research. The starting point is the importance of the institutional model of global governance for the effective control of non-proliferation of nuclear weapons. In this context, the research investigates how to structure the current arrangements of the international nuclear non-proliferation and what is the performance of model Mutual Vigilance Brazilian-Argentine of Nuclear Safeguards in relation to accountability regimes of global governance. For that, was searched the current literature of three theoretical dimensions: accountability, global governance and global governance organizations. In relation to the research method was used the case study and the treatment technique of data the analysis of content. The results allowed: to establish an evaluation model based on accountability mechanisms; to assess how behaves the model Mutual Vigilance Brazilian-Argentine Nuclear Safeguards front of the proposed accountability regime; and to measure the degree to which regional arrangements that work with systems of global governance can strengthen these international systems. (author)

  9. 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'.

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

    International Nuclear Information System (INIS)

    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

  11. 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.

  12. 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.

  13. The voluntary safeguards offer of the United States

    International Nuclear Information System (INIS)

    Houck, F.S.

    1985-01-01

    During negotiations of the Treaty on the Non-Proliferation of Nuclear Weapons (NPT) concerns were expressed by non-nuclear-weapon States that their acceptance of Agency safeguards would put them at a disadvantage vis-a-vis the nuclear-weapon States. To allay these concerns, the United States and the United Kingdom in December 1967 made voluntary offers to accept Agency safeguards on their peaceful nuclear activities. Subsequently, France made a voluntary offer, the safeguards agreement for which was approved by the IAEA Board of Governors in February 1978, with a view to encouraging acceptance of Agency safeguards by additional States. More recently, in February 1985 the Board approved the safeguards agreement for the voluntary offer of the USSR, made inter alia to encourage further acceptance of Agency safeguards. These safeguards agreements with nuclear-weapon-States have two important features in common: Namely, they result from voluntary offers to accept safeguards rather than from multilateral or bilateral undertakings, and they give the Agency the right but generally not an obligation to apply its safeguards. The agreements differ in certain respects, the most noteworthy of which is the scope of the nuclear activities covered by each offer. The agreements of the United States and United Kingdom are the broadest, covering all peaceful nuclear activities in each country. The safeguards agreement for the US voluntary offer has been in force since December 1980. Now is an appropriate time to review the experience with the agreement's implementation during its first four years, as well as its history and salient features

  14. International safeguards for reprocessing plants. Final report

    International Nuclear Information System (INIS)

    Kratzer, M.; Scheinman, L.; Sievering, N.; Wonder, E.; Lipman, D.; Immerman, W.; Elliott, J.M.; Crane, F.

    1981-04-01

    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

  15. International safeguards for reprocessing plants. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Kratzer, M.; Scheinman, L.; Sievering, N.; Wonder, E.; Lipman, D.; Immerman, W.; Elliott, J.M.; Crane, F.

    1981-04-01

    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.

  16. Agreement reached on integrated safeguards in European Union

    International Nuclear Information System (INIS)

    2010-01-01

    Full text: The International Atomic Energy Agency (IAEA), in cooperation with the European Commission, has reached agreement on arrangements to implement 'integrated safeguards' in all non-nuclear-weapon States of the European Union with significant nuclear activities. 'This important milestone is the result of the constructive common efforts of all parties concerned. It is a clear signal of the importance attributed by the EU and its Member States, as well as the IAEA, to the reinforcement of the nuclear non-proliferation regime,' said Andris Piebalgs, Member of the European Commission in charge of Energy. 'Once we have sufficient confidence that a State' s nuclear activities are purely peaceful, we can apply safeguards measures in a less prescriptive, more customised manner. This reduces the inspection burden on the State and the inspection effort of the IAEA, while enabling the IAEA to maintain the conclusion that all nuclear material has remained in peaceful activities,' said Olli Heinonen, Deputy Director General and Head of IAEA Safeguards Department. Background The Nuclear Non-Proliferation Treaty (NPT) is the main international Treaty prohibiting the spread of nuclear weapons. It entrusts the IAEA to verify that nuclear material is not diverted to nuclear weapons or other nuclear explosive devices through the application of 'safeguards'. IAEA safeguards include comprehensive safeguards agreements and additional protocols that enable the IAEA to conclude that all nuclear material has remained in peaceful activities in a State. Integrated Safeguards refers to the optimum combination of all safeguards measures available to the Agency under comprehensive safeguards agreements and additional protocols to achieve maximum effectiveness and efficiency in meeting the Agency ' s safeguards obligations. In the European Union, nuclear safeguards are implemented on the basis of the Euratom Treaty and trilateral agreements between Euratom, its Member States and the IAEA

  17. The future of IAEA safeguards: challenges and responses

    International Nuclear Information System (INIS)

    Pilat, Joseph F.; Budlong-Sylvester, Kory W.

    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 and D strategies needed to meet those challenges in the context of the forty-year evolution of safeguards, including the

  18. Integrated Safeguards proposal for Finland. Final report on Task FIN C 1264 of the Finnish Support Programme to IAEA Safeguards

    International Nuclear Information System (INIS)

    Anttila, M.

    2000-08-01

    The IAEA has requested several member states to present their proposal of the application of the Integrated Safeguards (IS) system in their nuclear facilities. This report contains a IS proposal for Finland prepared under the Task FIN C 1264 of The Finnish Support Programme to IAEA Safeguards. The comprehensive safeguards system of the International Atomic Energy Agency (IAEA) has been one of the main tools in the fight against nuclear proliferation since the entry-into-force of the Nuclear Non-proliferation Treaty three decades ago. In the 1990s some of the inherent weaknesses of this so-called traditional safeguards system were revealed first in Iraq and then in North Korea. Therefore, the member states of the LAEA decided to give the Agency additional legal authority in order to make its control system more effective as well as more efficient than before. This was accomplished by the approval of the so-called Model Additional Protocol (INFCIRC/540) in 1997. Straightforward implementation of new safeguards measures allowed by the Additional Protocol (INF-CIRC540) without careful review of the old procedures based on INFCIRC153 would only result in increased costs within the IAEA and in the member states. In order to avoid that kind of outcome the old and new means available to the Agency shall be combined to form an optimised integrated safeguards (IS) system. When creating an effective and efficient system a necessary approach is a state-level evaluation, which means that each state shall be assessed by the IAEA separately and as a whole. The assessment of a country's nuclear field shall result in credible assurance of the absence of diversion of declared nuclear materials to prohibited purposes and of the absence of clandestine nuclear activities, facilities and materials. Having achieved that assurance and being able to maintain it in a state the LAEA can leave some traditional routine safeguards activities undone there. At present, the nuclear fuel cycle in

  19. Redefining interrelationship between nuclear safety, nuclear security and safeguards

    International Nuclear Information System (INIS)

    Irie, Kazutomo

    2011-01-01

    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. The importance of the 3Ss is now emphasized to countries which are newly introducing nuclear power generation. However, as role models for those newcomers, existing nuclear power countries are also required to strengthen their regulatory infrastructure for the 3Ss. 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. Recently, it becomes quite difficult to clearly demarcate these policy tools. As nuclear security concept is expanding, the denotation of nuclear security measures is also expanding. Nuclear security measures are more and more

  20. Open source information acquisition, analysis and integration in the IAEA Department of Safeguards

    International Nuclear Information System (INIS)

    Barletta, M.; Zarimpas, N.; Zarucki, R.

    2010-10-01

    Acquisition and analysis of open source information plays an increasingly important role in the IAEA strengthened safeguards system. The Agency's focal point for open source information collection and analysis is the Division of Safeguards Information Management (SGIM) within the IAEA Department of Safeguards. In parallel with the approval of the Model Additional Protocol in 1997, a new centre of information acquisition and analysis expertise was created within SGIM. By acquiring software, developing databases, retraining existing staff and hiring new staff with diverse analytical skills, SGIM is pro actively contributing to the future implementation of information-driven safeguards in collaboration with other Divisions within the Department of Safeguards. Open source information support is now fully integrated with core safeguards processes and activities, and has become an effective tool in the work of the Department of Safeguards. This provides and overview of progress realized through the acquisition and use of open source information in several thematic areas: evaluation of additional protocol declarations; support to the State Evaluation process; in-depth investigation of safeguards issues, including assisting inspections and complementary access; research on illicit nuclear procurement networks and trafficking; and monitoring nuclear developments. Demands for open source information have steadily grown and are likely to continue to grow in the future. Coupled with the enormous growth and accessibility in the volume and sources of information, new challenges are presented, both technical and analytical. This paper discusses actions taken and future plans for multi-source and multi-disciplinary analytic integration to strengthen confidence in safeguards conclusions - especially regarding the absence of undeclared nuclear materials and activities. (Author)

  1. Legal instruments related to the application of safeguards

    International Nuclear Information System (INIS)

    Rockwood, Laura

    2001-01-01

    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)

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

    International Nuclear Information System (INIS)

    Naito, K.

    2013-01-01

    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)

  3. Cost/Benefit Prioritization for Advanced Safeguards Research and Development

    International Nuclear Information System (INIS)

    DeMuth, S.F.; Adeli, R.; Thomas, K.E.

    2008-01-01

    A system level study utilizing commercially available Extend TM software, has been initiated to perform cost/benefit analyses for advanced safeguards research and development. The methodology is focused on estimating standard error in the inventory difference (SEID) for reprocessing and fuel fabrication facilities, for various proposed advanced safeguards measurement technologies. The inventory duration, and consequent number of inventories per year, is dictated by the detection of a significant quantity of special nuclear material (SNM). Detection is limited by the cumulative measurement uncertainty for the entire system. The cost of inventories is then compared with the cost of advanced instrumentation and/or process design changes. Current progress includes development of the methodology, future efforts will be focused on ascertaining estimated costs and performance. Case studies will be provided as examples of the methodology. (author)

  4. Los Alamos National Laboratory Facilities, Security and Safeguards Division, Safeguards and Security Program Office, Protective Force Oversight Program

    International Nuclear Information System (INIS)

    1995-01-01

    The purpose of this document is to identify and describe the duties and responsibilities of Facility Security and Safeguards (FSS) Safeguards and Security (SS) organizations (groups/offices) with oversight functions over the Protection Force (PF) subcontractor. Responsible organizations will continue their present PF oversight functions under the Cost Plus Award Fee (CPAF) assessment, but now will be required to also coordinate, integrate, and interface with other FSS S and S organizations and with the PF subcontractor to measure performance, assess Department of Energy (DOE) compliance, reduce costs, and minimize duplication of effort. The role of the PF subcontractor is to provide the Laboratory with effective and efficient protective force services. PF services include providing protection for the special nuclear material, government property and classified or sensitive information developed and/or consigned to the Laboratory, as well as protection for personnel who work or participate in laboratory activities. FSS S and S oversight of both performance and compliance standards/metrics is essential for these PF objectives to be met

  5. Safeguards Summary Event List (SSEL)

    International Nuclear Information System (INIS)

    1991-07-01

    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

  6. Some reflections on nuclear safeguards

    International Nuclear Information System (INIS)

    Campbell, Ross.

    1981-01-01

    The author doubts whether, in view of the 1976 policy of requiring adherence to the Non-Proliferation Treaty or equivalent IAEA safeguards, Canada still needs the 1974 policy of bilateral safeguards on technology as well as material. The opinion is expressed that bilateral safeguards create difficulties for the IAEA, and are resented by some potential customers. Much better, if it were achievable, would be a code agreed by a convention of vendors and customers alike, to include sanctions against transgressors. The author expresses confidence in the IAEA, but perceives a need for more men and money. Also needed are better instruments to account for materials

  7. Global partnering related to nuclear materials safeguards and security - A pragmatic approach to international safeguards work

    International Nuclear Information System (INIS)

    Stanford, Dennis

    2007-01-01

    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)

  8. International safeguards problem

    International Nuclear Information System (INIS)

    Scheinman, L.; Curtis, H.B.

    1977-01-01

    To recognize the limitations of safeguards as a barrier to nuclear proliferation is not to deny their essential role in the effort to contain that problem. Without a safeguards system, international nuclear commerce and development would not, indeed could not, be what they are today. The problems evoked in the discussion of the spread of sensitive nuclear technology underscore the importance of ensuring that activities do not outpace our ability to control them. To sustain a global nuclear economy requires a readiness to live within the constraints that such an economy requires. Enhanced safeguards and strengthened national commitments to facilitate their application are key elements of those constraints. So also may be a prepardness by many nations to forego explicitly national control over all facets of the nuclear fuel cycle while still sharing fully and equally in the benefits of the peaceful atom. The challenge of the coming years will be to craft mechanisms and institutions enabling the continued growth of peaceful nuclear activity without further impairing international security. The constraints that such an outcome entails are not limited to nations lacking sophisticated nuclear technology; they apply to the most advanced nuclear nations as well--partly through adherence to the safeguards system that these countries call upon others to adopt, and partly through greater willingness to entertain solutions that may involve greater international involvement in, and control over, their own peaceful nuclear productive activities. With time, the relative incompatibility of nuclear energy with full national sovereignty, and the far-sighted wisdom of the Baruch Plan, are becoming increasingly clear. 1 table, 10 references

  9. Safeguards system testing WSRC Insider Exercise Program (U)

    International Nuclear Information System (INIS)

    Robichaux, J.J.

    1991-01-01

    One of the major concerns related to the control and accountability of nuclear material located at DOE facilities is the theft or diversion of material by an insider. Many complex safeguards and security systems have been installed to provide timely detection and prevention of the removal of nuclear materials. The Westinghouse Savannah River Company's (WSRC) Material Control and Accountability (MC and A) section has implemented an insider exercise program designed to evaluate the effectiveness of these safeguards systems. Exercises consist of limited scope performance test. This paper describes the structure and controls for the insider exercise program at the Savannah River Site, the lessons learned over the past several years, and methods being utilized to improve the program

  10. 77 FR 38033 - WTO Agricultural Safeguard Trigger Levels

    Science.gov (United States)

    2012-06-26

    ... DEPARTMENT OF AGRICULTURE Foreign Agricultural Service WTO Agricultural Safeguard Trigger Levels... and trigger levels for safeguard measures provided for in the World Trade Organization (WTO) Agreement... measures under the safeguard provisions of the WTO [[Page 38034

  11. Performance model for a CCTV-MTI

    International Nuclear Information System (INIS)

    Dunn, D.R.; Dunbar, D.L.

    1978-01-01

    CCTV-MTI (closed circuit television--moving target indicator) monitors represent typical components of access control systems, as for example in a material control and accounting (MC and A) safeguards system. This report describes a performance model for a CCTV-MTI monitor. The performance of a human in an MTI role is a separate problem and is not addressed here. This work was done in conjunction with the NRC sponsored LLL assessment procedure for MC and A systems which is presently under development. We develop a noise model for a generic camera system and a model for the detection mechanism for a postulated MTI design. These models are then translated into an overall performance model. Measures of performance are probabilities of detection and false alarm as a function of intruder-induced grey level changes in the protected area. Sensor responsivity, lens F-number, source illumination and spectral response were treated as design parameters. Some specific results are illustrated for a postulated design employing a camera with a Si-target vidicon. Reflectance or light level changes in excess of 10% due to an intruder will be detected with a very high probability for the portion of the visible spectrum with wavelengths above 500 nm. The resulting false alarm rate was less than one per year. We did not address sources of nuisance alarms due to adverse environments, reliability, resistance to tampering, nor did we examine the effects of the spatial frequency response of the optics. All of these are important and will influence overall system detection performance

  12. Nuclear material control and accounting safeguards in the United States

    International Nuclear Information System (INIS)

    Woltermann, H.A.; Rudy, C.R.; Rakel, D.A.; DeVer, E.A.

    1982-01-01

    Material control and accounting (MC and A) of special nuclear material (SNM) must supplement physical security to protect SNM from unlawful use such as terrorist activities. This article reviews MC and A safeguards of SNM in the United States. The following topics are covered: a brief perspective and history of MC and A safeguards, current MC and A practices, measurement methods for SNM, historical MC and A performance, a description of near-real-time MC and A systems, and conclusions on the status of MC and A in the United States

  13. Prioritizing and scheduling Portsmouth Gaseous Diffusion Plant safeguards upgrades

    International Nuclear Information System (INIS)

    Edmunds, T.; Saleh, R.; Zevanove, S.

    1992-02-01

    As part of the Site Safeguards and Security Plan (SSSP), facilities are required to develop a Resource Plan (RP). The Resource Plan provides documentation and justification for the facility's planned upgrades, including the schedule, priority, and cost estimates for the safeguards and security upgrades. Portsmouth Gaseous Diffusion Plant (PORTS) management has identified and obtained funding approval for a number of safeguards and security upgrades, including line-item construction projects. These upgrade projects were selected to address a variety of concerns identified in the PORTS vulnerability assessments and other reviews performed in support of the SSSP process. However, budgeting and scheduling constraints do not make it possible to simultaneously begin implementation of all of the upgrade projects. A formal methodology and analysis are needed to explicitly address the trade-offs between competing safeguards objectives, and to prioritize and schedule the upgrade projects to ensure that the maximum benefit can be realized in the shortest possible time frame. The purpose of this report is to describe the methodology developed to support these upgrade project scheduling decisions. The report also presents the results obtained from applying the methodology to a set of the upgrade projects selected by PORTS S ampersand S management. Data for the analysis are based on discussions with personnel familiar with the PORTS safeguards and security needs, the requirements for implementing these upgrades, and upgrade funding limitations. The analysis results presented here assume continued highly enriched uranium (HEU) operations at PORTS. However, the methodology developed is readily adaptable for the evaluation of other operational scenarios and other resource allocation issues relevant to PORTS

  14. Safeguards for the atom

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1959-10-15

    Concern over the destructive potentialities of nuclear energy has grown all over the world. In fact, it was this concern, coupled with an awareness of the equally great potentialities for peaceful prosperity, that led to the establishment of the International Atomic Energy Agency. That nuclear energy should be used solely for peaceful purposes is an ideal to which all people would subscribe. Realization of this ideal, however, is dependent on many complex factors which are outside the scope of the Agency. In its own limited sphere, however, the Agency has the responsibility to ensure that in its efforts to promote the peaceful uses it does not in any way increase the potentiality of military use. The possibility of military application is not the only danger that the Agency must guard against, it has a further function arising from the nature of the materials needed in atomic energy work. Since the basic materials are radioactive and since all ionizing radiation is potentially dangerous, the Agency must ensure that in helping its Member States to develop the peaceful uses of atomic energy it does not increase the hazards of nuclear radiation or radioactive contamination. It must establish standards of safe practice for activities carried out under its auspices or with its assistance. Since the safeguards will have two distinct objectives, a distinction can be made between those which will be designed to prevent the diversion of Agency assistance to military use and those against health and safety hazards. So far as the health and safety measures are concerned, a good deal of work has already been done in determining the standards of safe practice which will be the basis for the relevant rules. The Agency has published the first in its series of safety manuals, 'Safe Handling of Radioisotopes', which deals with such standards. Safeguards against the diversion or loss of nuclear materials and facilities are more difficult to devise. It is not considered feasible for

  15. Safeguards for the atom

    International Nuclear Information System (INIS)

    1959-01-01

    Concern over the destructive potentialities of nuclear energy has grown all over the world. In fact, it was this concern, coupled with an awareness of the equally great potentialities for peaceful prosperity, that led to the establishment of the International Atomic Energy Agency. That nuclear energy should be used solely for peaceful purposes is an ideal to which all people would subscribe. Realization of this ideal, however, is dependent on many complex factors which are outside the scope of the Agency. In its own limited sphere, however, the Agency has the responsibility to ensure that in its efforts to promote the peaceful uses it does not in any way increase the potentiality of military use. The possibility of military application is not the only danger that the Agency must guard against, it has a further function arising from the nature of the materials needed in atomic energy work. Since the basic materials are radioactive and since all ionizing radiation is potentially dangerous, the Agency must ensure that in helping its Member States to develop the peaceful uses of atomic energy it does not increase the hazards of nuclear radiation or radioactive contamination. It must establish standards of safe practice for activities carried out under its auspices or with its assistance. Since the safeguards will have two distinct objectives, a distinction can be made between those which will be designed to prevent the diversion of Agency assistance to military use and those against health and safety hazards. So far as the health and safety measures are concerned, a good deal of work has already been done in determining the standards of safe practice which will be the basis for the relevant rules. The Agency has published the first in its series of safety manuals, 'Safe Handling of Radioisotopes', which deals with such standards. Safeguards against the diversion or loss of nuclear materials and facilities are more difficult to devise. It is not considered feasible for

  16. Work Group 1: Future Directions for International Safeguards

    International Nuclear Information System (INIS)

    Casterton, J.; Meylemans, P.

    2013-01-01

    The State-Level Concept (SLC) is a holistic approach to safeguards implementation, applicable to all States with safeguards agreements. It is based on a comprehensive and continuous State evaluation and a State level approach for each State, including a specific combination of safeguards measures. It is executed through an annual implementation plan. The SLC has the value of considering the State as a whole. It provides the opportunity to take State-specific factors into account through all stages of safeguards implementation. The implementation of the SLC permits the IAEA to be responsive to all kinds of changes arising from continuous analysis. As a result the safeguards conclusions remain soundly based and up-to-date. The SLC is implemented by the IAEA as a continuous process involving three major components: establishing knowledge about the State and drawing conclusions, determining the specific State level approach, and planning and implementing safeguards activities. The major products that emerge from this process are the State level approach, the annual implementation plan that is the basis for implementing safeguards activities in a State on an annual basis, and the safeguards conclusions, which are set out in the Safeguards Implementation Report on an annual basis. A better cooperation between IAEA and SSAC (State Systems of Accounting for and Control of nuclear material), RSAC (Regional State Systems of Accounting for and Control of nuclear material is important for developing and implementing SLC. The paper is followed by the slides of the presentation. (A.C.)

  17. Safeguards technology development for spent fuel storage and disposal

    International Nuclear Information System (INIS)

    Sanders, K.E.

    1991-01-01

    This paper reports on facilities for monitored retrievable storage and geologic repository that will be operating in the US by 1998 and 2010 respectively. The international safeguards approach for these facilities will be determined broadly by the Safeguards Agreement and the IAEA Safeguards Criteria (currently available for 1991-1995) and defined specifically in the General Subsidiary Arrangements and Specific Facility Attachments negotiated under the US/IAEA Safeguards Agreement. Design information for these facilities types, as it is conceptualized, will be essential input to the safeguards approach. Unique design and operating features will translate into equally unique challenges to the application of international safeguards. The development and use of new safeguards technologies offers the greatest potential for improving safeguards. The development and use of new safeguards technologies offers the greatest potential for improving safeguards by enabling efficient and effective application with regard to the operator's interest, US policies, and the IAEA's statutorial obligations. Advanced unattended or remote measurement, authentication of operator's measurement, authentication of operator's measurement data, and integration of monitoring and containment/surveillance potentially are among the most fruitful areas of technology development. During the next year, a long range program plan for international safeguard technology development for monitored retrievable storage and geologic repository will be developed by the International Branch in close coordination with the Office of Civilian Radioactive Waste Management. This presentation preliminarily identifies elements of this long range program

  18. Societal risk approach to safeguards design and evaluation

    International Nuclear Information System (INIS)

    Bennett, C.A.; Murphey, W.M.; Sherr, T.S.

    1975-06-01

    There has been much discussion and public debate concerning the effectiveness of the national system of safeguards against malevolent acts involving nuclear materials. Useful dialogue on this subject has been hampered by the lack of well-defined objectives, system parameters and boundary conditions as a framework for communication. This study provides such a framework. Expressing the safeguards objective in terms of societal risk represents a change in focus, rather than intent, from the earlier view of safeguards as a system for protecting nuclear material against theft or diversion. The study defines both the safeguards problem and the safeguards system in terms that can be related to the general safeguards objective. It is axiomatic that the first step to an effective solution is a careful definition of the problem. The significant and immediate value of this study lies in the rigorous definition and systematic organization of recognized elements into a coherent and comprehensive pattern. Although the title specifically addresses design and evaluation, the framework provided by the study will be a useful management tool for safeguards implementation and administration as well. (U.S.)

  19. 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.

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

    International Nuclear Information System (INIS)

    Smith, D.B.

    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

  1. Non-proliferation and international safeguards. [Booklet by IAEA

    Energy Technology Data Exchange (ETDEWEB)

    1978-01-01

    This booklet consists of 13 separate, brief analyses related to the subject title, namely: The International Scope of IAEA Safeguards; Application of Safeguards Procedures; Computer-Based Safeguards Information and Accounting System; IAEA Training Activities Related to State Systems of Nuclear Materials Accountancy and Control; Surveillance and Containment Measures to Support IAEA Safeguards; International Plutonium Management; Safeguards for Reprocessing and Enrichment Plants; Non-Destructive Assay: Instruments and Techniques for Agency Safeguards; The Safeguards Analytical Laboratory: Its Functions and Analytical Facilities; Resolution of the UN General Assembly on the Treaty on the Non-Proliferation of Nuclear Weapons of 12 June 1968; The Treaty on the Non-Proliferation of Nuclear Weapons; Final Declaration of the Review Conference of the Parties to the Treaty on the Non-Proliferation of Nuclear Weapons, May 1975; Resolutions on the IAEA's Work in the Field of the Peaceful Uses of Atomic Energy, adopted by the UN General Assembly on 8 and 12 December, 1977; and a Map on the NPT situation in the world (with explanations).

  2. Prospects for regional safeguards systems - State-level Approach

    International Nuclear Information System (INIS)

    Peixoto, O.J.M.

    2013-01-01

    The increased co-operation with Regional Safeguard's System (RSAC) is a relevant tool for strengthening effectiveness and improving the efficiency of the international safeguard. The new safeguards system that emerges from the application of the Additional Protocol (INFCIRC/540) and the full use of State-level Concept is a challenge and an opportunity for effectively incorporate RSAC into the international safeguards scheme. The challenge is to determine how the co-operation and coordination will be implemented on this new safeguards scheme. This paper presents some discussions and prospects on the issues to be faced by RSAC and IAEA during the implementation of State-level Approach (SLA) using all information available. It is also discussed how different levels of co-operation could be achieved when SLA is applied by IAEA safeguards. The paper is followed by the slides of the presentation. (authors)

  3. Simulation of nuclear fuel reprocessing for safeguards

    International Nuclear Information System (INIS)

    Canty, M.J.; Dayem, H.A.; Kern, E.A.; Spannagel, G.

    1983-11-01

    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.) [de

  4. The International Atomic Energy Agency's safeguards system

    International Nuclear Information System (INIS)

    Wagner, W.

    2000-01-01

    A system of international safeguards has been established to provide assurance that nuclear materials in civilian use are not diverted from their peaceful purpose. The safeguards system is administered by the International Atomic Energy Agency/Department of Safeguards and devolves from treaties and other international agreements. Inspectors from the Agency verify reports from States about nuclear facilities by audits, observation, and measurements. (author)

  5. International Atomic Energy agency use of facility calorimeters for safeguards purposes

    International Nuclear Information System (INIS)

    Mcrae, L.P.

    1996-01-01

    The IAEA is performing nuclear materials safeguards on an inventory of pure and scrap plutonium oxide powder materials held in Vault 3 of the Plutonium Finishing Plant at the Hanford Site,Washington State. The IAEA uses qualitative and quantitative techniques (weighing, sampling, and destructive analyses) to verify the presence and quantity of the nuclear materials under safeguards. In contrast, the plant operator generally uses non-destructive plutonium assay based on gamma spectrometry and calorimetry for its most accurate plutonium powder container measurements. Recent results have shown that the operator's calorimeter system achieves measurement variabilities comparable with, or better than, the destructive analyses, particularly for scrap. The results are achieved more quickly and economically,with less waste and lower radiation exposure and contamination hazard, by calorimetry than by classical destructive analyses.Techniques, including authentication methods, are being jointly developed to permit use of the operator's calorimeter system for international safeguards purposes. The authentication is to ensure the independence of, and to substantiate the validity of,calorimeter measurements for international safeguards. The authentication methods considered and being developed are discussed

  6. IAEA safeguards: some pros and cons

    International Nuclear Information System (INIS)

    Kelly, P.

    1986-01-01

    The author gives a personal view of the International Atomic Energy Agency's (IAEA) safeguards. The IAEA safeguards system is described (including containment, surveillance and inspection), and the limitations and strengths of the system are examined. (U.K.)

  7. National safeguard systems - Inspector formation

    International Nuclear Information System (INIS)

    Pontes, B.C.

    1986-01-01

    The safeguards' inspector profile, in consequence of the tasks to be performed is described. An activities'hierarchy which will lead, to the structure and content of an introductory course's curriculum is established. The auditing activity as well as the material verification are described in details. Complementary resources for the upgrading the inspector's knowledge and skills are analised and the paper concludes presenting the training period, its dinamics as well as the recrutment criterium for the candidates. (Author) [pt

  8. Open source information acquisition, analysis and integration in the IAEA Department of Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Barletta, M.; Zarimpas, N.; Zarucki, R., E-mail: M.Barletta@iaea.or [IAEA, Wagramerstrasse 5, P.O. Box 100, 1400 Vienna (Austria)

    2010-10-15

    Acquisition and analysis of open source information plays an increasingly important role in the IAEA strengthened safeguards system. The Agency's focal point for open source information collection and analysis is the Division of Safeguards Information Management (SGIM) within the IAEA Department of Safeguards. In parallel with the approval of the Model Additional Protocol in 1997, a new centre of information acquisition and analysis expertise was created within SGIM. By acquiring software, developing databases, retraining existing staff and hiring new staff with diverse analytical skills, SGIM is pro actively contributing to the future implementation of information-driven safeguards in collaboration with other Divisions within the Department of Safeguards. Open source information support is now fully integrated with core safeguards processes and activities, and has become an effective tool in the work of the Department of Safeguards. This provides and overview of progress realized through the acquisition and use of open source information in several thematic areas: evaluation of additional protocol declarations; support to the State Evaluation process; in-depth investigation of safeguards issues, including assisting inspections and complementary access; research on illicit nuclear procurement networks and trafficking; and monitoring nuclear developments. Demands for open source information have steadily grown and are likely to continue to grow in the future. Coupled with the enormous growth and accessibility in the volume and sources of information, new challenges are presented, both technical and analytical. This paper discusses actions taken and future plans for multi-source and multi-disciplinary analytic integration to strengthen confidence in safeguards conclusions - especially regarding the absence of undeclared nuclear materials and activities. (Author)

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

    International Nuclear Information System (INIS)

    1998-01-01

    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)

  10. The IAEA's safeguards system. Ready for the 21st century

    International Nuclear Information System (INIS)

    1997-09-01

    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?

  11. Integrated safeguards testing laboratories in support of the advanced fuel cycle initiative

    International Nuclear Information System (INIS)

    Santi, Peter A.; Demuth, Scott F.; Klasky, Kristen L.; Lee, Haeok; Miller, Michael C.; Sprinkle, James K.; Tobin, Stephen J.; Williams, Bradley

    2009-01-01

    A key enabler for advanced fuel cycle safeguards research and technology development for programs such as the Advanced Fuel Cycle Initiative (AFCI) is access to facilities and nuclear materials. This access is necessary in many cases in order to ensure that advanced safeguards techniques and technologies meet the measurement needs for which they were designed. One such crucial facility is a hot cell based laboratory which would allow developers from universities, national laboratories, and commercial companies to perform iterative research and development of advanced safeguards instrumentation under realistic operating conditions but not be subject to production schedule limitations. The need for such a facility arises from the requirement to accurately measure minor actinide and/or fission product bearing nuclear materials that cannot be adequately shielded in glove boxes. With the contraction of the DOE nuclear complex following the end of the cold war, many suitable facilities at DOE sites are increasingly costly to operate and are being evaluated for closure. A hot cell based laboratory that allowed developers to install and remove instrumentation from the hot cell would allow for both risk mitigation and performance optimization of the instrumentation prior to fielding equipment in facilities where maintenance and repair of the instrumentation is difficult or impossible. These benefits are accomplished by providing developers the opportunity to iterate between testing the performance of the instrumentation by measuring realistic types and amounts of nuclear material, and adjusting and refining the instrumentation based on the results of these measurements. In this paper, we review the requirements for such a facility using the Wing 9 hot cells in the Los Alamos National Laboratory's Chemistry and Metallurgy Research facility as a model for such a facility and describe recent use of these hot cells in support of AFCI.

  12. Integrated safeguards testing laboratories in support of the advanced fuel cycle initiative

    Energy Technology Data Exchange (ETDEWEB)

    Santi, Peter A [Los Alamos National Laboratory; Demuth, Scott F [Los Alamos National Laboratory; Klasky, Kristen L [Los Alamos National Laboratory; Lee, Haeok [Los Alamos National Laboratory; Miller, Michael C [Los Alamos National Laboratory; Sprinkle, James K [Los Alamos National Laboratory; Tobin, Stephen J [Los Alamos National Laboratory; Williams, Bradley [DOE, NE

    2009-01-01

    A key enabler for advanced fuel cycle safeguards research and technology development for programs such as the Advanced Fuel Cycle Initiative (AFCI) is access to facilities and nuclear materials. This access is necessary in many cases in order to ensure that advanced safeguards techniques and technologies meet the measurement needs for which they were designed. One such crucial facility is a hot cell based laboratory which would allow developers from universities, national laboratories, and commercial companies to perform iterative research and development of advanced safeguards instrumentation under realistic operating conditions but not be subject to production schedule limitations. The need for such a facility arises from the requirement to accurately measure minor actinide and/or fission product bearing nuclear materials that cannot be adequately shielded in glove boxes. With the contraction of the DOE nuclear complex following the end of the cold war, many suitable facilities at DOE sites are increasingly costly to operate and are being evaluated for closure. A hot cell based laboratory that allowed developers to install and remove instrumentation from the hot cell would allow for both risk mitigation and performance optimization of the instrumentation prior to fielding equipment in facilities where maintenance and repair of the instrumentation is difficult or impossible. These benefits are accomplished by providing developers the opportunity to iterate between testing the performance of the instrumentation by measuring realistic types and amounts of nuclear material, and adjusting and refining the instrumentation based on the results of these measurements. In this paper, we review the requirements for such a facility using the Wing 9 hot cells in the Los Alamos National Laboratory's Chemistry and Metallurgy Research facility as a model for such a facility and describe recent use of these hot cells in support of AFCI.

  13. Canada and international safeguards. Verifying nuclear non-proliferation

    International Nuclear Information System (INIS)

    1990-01-01

    The Non-Proliferation Treaty (NPT) came into force in 1970 and now has about 140 signatory nations. By creating legal barriers against proliferation and by promoting an international non-proliferation ethic, the NPT has promoted international peace and security. A key ingredient has been the confidence generated through verification by IAEA safeguards. By the end of 1988 IAEA safeguards agreements had been concluded with about 100 countries, including Canada. Over 500 nuclear facilities worldwide are under safeguards or contain safeguarded nuclear material. The existence of this credible and effective safeguards system makes international trade in nuclear equipment and materials possible, monitoring the transfer of nuclear technology to developing countries as well as between industrial countries. Canada is committed to non-proliferation and IAEA safeguards. Canadian non-proliferation policy is among the strictest in the world, even though opportunities have been lost to sell Canadian technology abroad as a result

  14. Middle term prospects for Japan's safeguards

    International Nuclear Information System (INIS)

    Ogawa, T.

    2001-01-01

    Japan has responded to IAEA requirements on reinforced safeguard regulations. The IAEA additional protocol entered in force in Japan on December 1999. Japan submitted a preliminary information report to IAEA on June 2000 after joint works with the Nuclear Material Control Center (NMCC) of Japan. The first annual report was submitted to IAEA on May 2001. Another activity for the additional protocol is complementary accesses. The total 36 accesses to facilities have been done from November 2000 to September 2001. Procedures of access to managements are under discussion. MEXT (Ministry of Education, Culture, Sports, Science and Technology) has been constructing the Rokkasho Safeguards On-Site Laboratory from 1997, and the Rokkasho Safeguards Center from 2000. The Design Information Verification (DIV) is now ongoing. Much more personal resources will be needed for future inspections. Therefore, the budget for safeguards is increasing in contrast to the flat base budget for the total atomic energy. As for future activity, a MOX (Mixed Oxide Fuels) fuel processing plant is one of the issues for discussion. The construction of the MOX processing plant is supposed to begin on around 2004. The conclusion of additional protocol will be given by IAEA until end of 2002. Shift to integrated safeguards are under discussions by MEXT, NMCC and utilities of Japan parallel with IAEA. Key issues of discussion are cost saving for safeguards, development of personal resources for inspectors and the role of NMCC. (Y. Tanaka)

  15. IAEA safeguards: Staying ahead of the game

    International Nuclear Information System (INIS)

    2007-07-01

    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. Developing a simulation for border safeguarding

    CSIR Research Space (South Africa)

    Van Rooyen, S

    2011-09-01

    Full Text Available Border safeguarding is the defence of territorial integrity and sovereignty, and this is a joint responsibility of the military and the police. Military doctrine for conventional warfare is not sufficient for Border Safeguarding operations due...

  17. Next Generation Germanium Systems for Safeguards Applications

    International Nuclear Information System (INIS)

    Dreyer, J.; Burks, M.; Hull, E.

    2015-01-01

    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)

  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. Points for Improvement in Mexican Legislation on Safeguards

    International Nuclear Information System (INIS)

    Maciel Sánchez, S.; Carreño Padilla, A. L.

    2015-01-01

    The main goal of this paper is to underline the specific points needed still to be improved on safeguards in the Mexican legal framework. The problem: Mexico proposed the Tlatelolco Treaty which was before the TNP. So the Mexican legislation on safeguards should to be one of the best around the world, but there are still points to be improved, such as a specific regulation on the topic. Justification: Remembering that the exact sciences need of the law in order to be applied in a desirable way. I mean, the safeguards could be well conceived and well worked from the physics and mathematics point of view, but in order to be followed in any country, it is necessary the right legal framework. Hypothesis: What has Mexico now in its legislation on safeguards and what remains to be done (what is pending in the Mexican legal scope of the safeguards)? Objectives: – To propose legal solutions to correct the weakness of the Mexican legal framework on Safeguards; taking into account my own experience drafting the Mexican regulation on safeguards from 2008 for the Mexican Government in my nuclear law firm “Martínez and Maciel”. – To propose a legal framework on safeguards for Mexico as it is understood by the IAEA. – To update the legal frame work on safeguards in Mexico linking it to the Back end of the spent fuel. (Considering that sooner or later the Mexican Government will have to define its politic on this topic). (author)

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

    International Nuclear Information System (INIS)

    Smith, D.B.

    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

  1. The Concept of Goals-Driven Safeguards

    International Nuclear Information System (INIS)

    Wigeland, R.; Bjornard, T.; Castle, B.

    2009-01-01

    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.

  2. IAEA safeguards for the Fissile Materials Disposition Project

    International Nuclear Information System (INIS)

    Close, D.A.

    1995-06-01

    This document is an overview of International Atomic Energy Agency (IAEA) safeguards and the basic requirements or elements of an IAEA safeguards regime. The primary objective of IAEA safeguards is the timely detection of the diversion of a significant quantity of material and the timely detection of undeclared activities. The two important components of IAEA safeguards to accomplish their primary objective are nuclear material accountancy and containment and surveillance. This overview provides guidance to the Fissile Materials Disposition Project for IAEA inspection requirements. IAEA requirements, DOE Orders, and Nuclear Regulatory Commission regulations will be used as the basis for designing a safeguards and security system for the facilities recommended by the Fissile Materials Disposition Project

  3. Nuclear proliferation-resistance and safeguards for future nuclear fuel cycle

    International Nuclear Information System (INIS)

    Kuno, Y.; Inoue, N.; Senzaki, M.

    2009-01-01

    Corresponding to the world nuclear security concerns, future nuclear fuel cycle (NFC) should have high proliferation-resistance (PR) and physical protection (PP), while promotion of the peaceful use of the nuclear energy must not be inhibited. In order to accomplish nuclear non-proliferation from NFC, a few models of the well-PR systems should be developed so that international community can recognize them as worldwide norms. To find a good balance of 'safeguard-ability (so-called extrinsic measure or institutional barrier)' and 'impede-ability (intrinsic feature or technical barrier)' will come to be essential for NFC designers to optimize civilian nuclear technology with nuclear non-proliferation, although the advanced safeguards with high detectability can still play a dominant role for PR in the states complying with full institutional controls. Accomplishment of such goal in a good economic efficiency is a future key challenge

  4. Nuclear proliferation-resistance and safeguards for future nuclear fuel cycle

    Science.gov (United States)

    Kuno, Y.; Inoue, N.; Senzaki, M.

    2009-03-01

    Corresponding to the world nuclear security concerns, future nuclear fuel cycle (NFC) should have high proliferation-resistance (PR) and physical protection (PP), while promotion of the peaceful use of the nuclear energy must not be inhibited. In order to accomplish nuclear non-proliferation from NFC, a few models of the well-PR systems should be developed so that international community can recognize them as worldwide norms. To find a good balance of 'safeguard-ability (so-called extrinsic measure or institutional barrier)' and 'impede-ability (intrinsic feature or technical barrier)' will come to be essential for NFC designers to optimize civilian nuclear technology with nuclear non-proliferation, although the advanced safeguards with high detectability can still play a dominant role for PR in the states complying with full institutional controls. Accomplishment of such goal in a good economic efficiency is a future key challenge.

  5. Safeguards-By-Design: Guidance and Tools for Stakeholders

    Energy Technology Data Exchange (ETDEWEB)

    Mark Schanfein; Shirley Johnson

    2012-02-01

    Effective implementation of the Safeguards-by-Design (SBD) approach can help meet the challenges of global nuclear energy growth, by designing facilities that have improved safeguardability and reduced safeguards-related life cycle costs. The ultimate goal of SBD is to implement effective and efficient safeguards that reduce the burden to both the facility operator and the International Atomic Energy Agency. Since 2008, the National Nuclear Security Administration's Next Generation Safeguards Initiative's Safeguards By Design Project has initiated multiple studies and workshops with industry and regulatory stakeholders, including the IAEA, to develop relevant documents to support the implementation of SBD. These 'Good Practices Guides' describe facility and process design features that will facilitate implementation of effective nuclear material safeguards starting in the earliest phases of design through to final design. These guides, which are in their final editorial stages, start at a high level and then narrow down to specific nuclear fuel cycle facilities such as Light Water Reactors, Generation III/IV Reactors, High Temperature Gas Cooled Reactors, and Gas Centrifuge Enrichment Plants. Most recently, NGSI has begun development of a facility safeguardability assessment toolkit to assist the designer. This paper will review the current status of these efforts, provide some examples of these documents, and show some standard IAEA Unattended Instrumentation that is permanently installed in nuclear facilities for monitoring.

  6. Safeguards-By-Design: Guidance and Tools for Stakeholders

    International Nuclear Information System (INIS)

    Schanfein, Mark; Johnson, Shirley

    2012-01-01

    Effective implementation of the Safeguards-by-Design (SBD) approach can help meet the challenges of global nuclear energy growth, by designing facilities that have improved safeguardability and reduced safeguards-related life cycle costs. The ultimate goal of SBD is to implement effective and efficient safeguards that reduce the burden to both the facility operator and the International Atomic Energy Agency. Since 2008, the National Nuclear Security Administration's Next Generation Safeguards Initiative's Safeguards By Design Project has initiated multiple studies and workshops with industry and regulatory stakeholders, including the IAEA, to develop relevant documents to support the implementation of SBD. These 'Good Practices Guides' describe facility and process design features that will facilitate implementation of effective nuclear material safeguards starting in the earliest phases of design through to final design. These guides, which are in their final editorial stages, start at a high level and then narrow down to specific nuclear fuel cycle facilities such as Light Water Reactors, Generation III/IV Reactors, High Temperature Gas Cooled Reactors, and Gas Centrifuge Enrichment Plants. Most recently, NGSI has begun development of a facility safeguardability assessment toolkit to assist the designer. This paper will review the current status of these efforts, provide some examples of these documents, and show some standard IAEA Unattended Instrumentation that is permanently installed in nuclear facilities for monitoring.

  7. 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.

  8. Safeguards at NRC licensed facilities: Are we doing enough

    International Nuclear Information System (INIS)

    Asselstine, J.K.

    1986-01-01

    Safeguards at the Nuclear Regulatory Commission (NRC) facilities are discussed in this paper. The NRC is pursuing a number of initiatives in the safeguards area. The Commission is conducting a reassessment of its safeguards design basis threat statements to consider the possible implications of an explosive-laden vehicle for U.S. nuclear safeguards and to examine the comparability of safeguards features at NRC-licensed and DOE facilities. The Commission is also completing action on measures to protect against the sabotage threat from an insider at NRC-licensed facilities, and is examining the potential safety implications of safeguards measures. Finally, the NRC has developed measures to reduce the theft potential for high-enriched uranium

  9. Introduction of designated organization to safeguards implementation in Japan

    International Nuclear Information System (INIS)

    Terada, Hiromi; Akiba, Mitsunori; Ando, Hisataka; Okazaki, Shuji; Irikura, Masatoshi; Kurihara, Hiroyoshi

    2000-01-01

    With domestic application of the IAEA new measures (program 93+2) for strengthening the effectiveness and improving the efficiency of the safeguards system, the Nuclear Regulation Laws was amended for implementation of the new measures based upon the Additional Protocol, and also the new Designated Organization System was introduced to the SSAC (States' System of Accounting for and Control of Nuclear Materials) for safeguards implementation in Japan since beginning of January 2000. On the basis of accumulated experiences of the state safeguards implementation for more than 20 years and then established standardization of the inspection procedures, the Japan's Government is able to utilize the expertise of private organizations for the safeguards implementation. Any capable organizations can be designated by the Government as the Designated Organization for all or a part of safeguards implementations on behalf of the Government. According to the amended Law, the Prime Minister can make the Designated Organization implement safeguards implementations that are defined firstly as safeguards inspections which can be done along the Government instructions without any discussions and decisions, secondarily as destructive analysis of safeguards samples, and thirdly as technical research on advanced safeguards measures. The amendment of the Law was approved by the National Diet on June 9th 1999 and entered into force on December 16th 1999. The Additional Protocol also entered into force in Japan at the same time. The NMCC (Nuclear Material Control Center) was designated as the Organization on December 27th 1999 and started the safeguards implementation in January 7th 2000. In order to prepare for the Designated Organization, the NMCC rearranged the organizational system and kept capable human resources enough for the safeguards implementations. Also the NMCC carried out many programs of education and training for the inspectors. Furthermore, manuals and criteria for the

  10. International seminar on safeguards information reporting and processing. Extended synopses

    International Nuclear Information System (INIS)

    1998-01-01

    Review of the safeguards of information technology, its current developments and status of safeguards in Member States are described concerning especially the role of domestic safeguards in cooperation with IAEA Safeguards. A Number of reports is dealing with declarations provided to the IAEA pursuant to Protocols Additional to Safeguard agreements. The Information Section of the IAEA Safeguards Information Technology Division is responsible for the data entry, loading and quality control od State supplied declarations. A software system is used to process information which should be readily accessible and usable in implementation of the strengthened safeguards system. Experiences in combating illegal trafficking of nuclear materials in a number of countries are included

  11. From safeguards to treaty verification and the future

    International Nuclear Information System (INIS)

    Harry, J.

    1997-01-01

    Changes in safeguards techniques and changes in the context in which it has to be applied have led to a continuous evolution of safeguards. Nuclear material accountancy and its verification is still the basis of safeguards. But also other, less technical, tools are developed for the future. Will safeguards not become an idle story but continue to lay effectively and efficiently a concrete foundation for international trust and peace, there is a need for more investment in new methods and techniques to allow safeguards to keep pace with the developments, both politically and technically. Safeguards serves the international community by enhancing the mutual trust that leads to national security. That also enabled the rapid growth of international co-operation on the applications of nuclear energy. But international security is based on confidence. It is not a priori the technique that creates that sphere of confidence, the human and political interactions are at least equally important. In different cultures there are marked differences in behaviour and such differences can be easily misinterpreted. Therefore also the new safeguards has to be equally objectively established and critically executed under the close attention of all parties concerned

  12. Inspection methods for safeguards systems at nuclear facilities

    International Nuclear Information System (INIS)

    Minichino, C.; Richard, E.W.

    1981-01-01

    A project team at Lawrence Livermore National Laboratory has been developing inspection procedures and training materials for the NRC inspectors of safeguards systems at licensed nuclear facilities. This paper describes (1) procedures developed for inspecting for compliance with the Code of Federal Regulations, (2) training materials for safeguards inspectors on technical topics related to safeguards systems, such as computer surety, alarm systems, sampling techniques, and power supplies, and (3) an inspector-oriented methodology for evaluating the overall effectiveness of safeguards systems

  13. Quality assurance procedures for the IAEA Department of Safeguards Twin Minolta Camera Surveillance System

    International Nuclear Information System (INIS)

    Geoffrion, R.R.; Bussolini, P.L.; Stark, W.A.; Ahlquist, A.J.; Sanders, K.E.; Rubinstein, G.

    1986-01-01

    The International Atomic Energy Agency (IAEA) safeguards program provides assurance to the international community that nations are complying with nuclear safeguards treaties. In one aspect of the program, the Department of Safeguards has developed a twin Minolta camera photo surveillance systems program to assure itself and the international community that material handling is accomplished according to safeguards treaty regulations. The camera systems are positioned in strategic locations in facilities such that objective evidence can be obtained for material transactions. The films are then processed, reviewed, and used to substantiate the conclusions that nuclear material has not been diverted. Procedures have been developed to document and aid in: 1) the performance of activities involved in positioning of the camera system; 2) installation of the systems; 3) review and use of the film taken from the cameras

  14. Safeguarding uranium enrichment facilities. Review and analysis of the status of safeguards technology for uranium enrichment facilities

    International Nuclear Information System (INIS)

    1977-09-01

    The objective of this paper is to examine critically the diversion potential at uranium enrichment facilities and to outline a basic safeguards strategy which counters all identified hazards as completely as possible yet with a minimum of non-essential redundancy. Where existing technology does not appear to be adequate for effective safeguards, the limitations are examined, and suggestions for further R and D effort are made. Parts of this report are generally applicable to all currently known enrichment processes, while other parts are specifically directed toward facilities based on the gas centrifuge process. It is hoped that additional sections discussing a safeguards strategy for gas diffusion facilities can be added later. It should be emphasized that this is a technical report, and does not reflect any legal positions. The safeguards strategy and subsequent inspection procedures are intended as guidelines, not as negotiating positions

  15. Psychology of nuclear safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Parker, L [Manchester Univ. (UK)

    1978-08-17

    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.

  16. IAEA safeguards information system

    International Nuclear Information System (INIS)

    Nardi, J.

    1984-01-01

    The basic concepts, structure, and operation of the Agency Safeguards Information System is discussed with respect to its role in accomplishing the overall objectives of safeguards. The basis and purposes of the Agency's information system, the structure and flow of information within the Agency's system, the relationship of the components is the Agency system, the requirements of Member States in respect of their reporting to the Agency, and the relationship of accounting data vis-a-vis facility and inspection data are described

  17. The present status of IAEA safeguards on nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    1978-11-01

    The present IAEA approach to safeguarding various types of nuclear facilities is examined. The IAEA safeguards objectives, criteria and specific techniques are addressed, with reference e.g. to concepts like timely detection, quantities of safeguards significance, and conversion times. Material accountancy and containment and surveillance as basic features of IAEA safeguards verification are discussed. Safeguards measures for specific facility types are considered and corresponding levels of IAEA safeguards experience are assessed. Outlines of expected IAEA safeguard approaches to large bulk handling facilities are discussed. The evolutionary nature of safeguards based on experience and research and development is mentioned

  18. Development of an advanced safeguards system as a proliferation deterrent

    International Nuclear Information System (INIS)

    Ayers, A.A.; Barnes, L.D.

    1978-11-01

    The Advanced Safeguards System consists of Computerized Nuclear Materials Control and Accounting System, Physical Protection System, and Safeguards Coordination Center (SCC). Should all the computer-based monitoring systems be overcome (i.e., the NMC computer programmed not to recognize a materials inventory change, the SCC computer programmed to accept a falsified area and personnel authorization, and the physical security system programmed not to alarm for area intrusion), the requirements of the physical security system remain formidable barriers to successful theft since all SNM is separated from the uncontrolled areas by at least one entry control portal. An egress from the protected area--by either a vehicle through the vehicle access portal, or on foot through the personnel access portal--requires that the individuals be subjected to a search for metal and SNM before egress is permitted. The material access areas are further controlled by an interior access portal imposing the same SNM and metal search criteria. The portal search criteria are not subject to computer interpretation, but direct positive--negative indications to the portal patrolman. The physical security system then provides an independent backup should the computerized systems be defeated. Thus, the computer systems themselves will not, if defeated, guarantee an adversary success. The corollary also holds true; a defeat of the physical search elements of the physical security system will not guarantee adversary success because of the monitoring/surveillance function of the computerized systems. The complementary and overlapping nature of the safeguards systems is intended to provide multiple layers of safeguards, each layer providing an effective element of protection. Tests to date indicate that it appears feasible to meet operational objectives and maintain a high safeguards performance level using these concepts which are being incorporated into the Advanced Safeguards System.None

  19. Development of nuclear materials accounting for international safeguards

    International Nuclear Information System (INIS)

    Markin, J.T.; Augustson, R.H.; Eccleston, G.W.; Hakkila, E.A.

    1991-01-01

    This paper reports that nuclear materials accountancy was introduced as a primary safeguards measure in international safeguards at the inception of the EURATOM safeguards directorate in 1959 and in IAEA safeguards in 1961 with the issuance of INFCIRC 26. As measurement technology evolved and safeguarded facilities increased in both number and size, measurement methodology requirements increased as reflected in INFCIRC 66 (Rev 2.) in 1968 and later in INFCIRC 153 in 1972. Early measurements relied heavily on chemical analysis, but in the 1960s the measurements evolved more and more toward nondestructive assay. Future nuclear materials accountancy systems will increase in complexity, driven by larger and more complex facilities; more stringent health, safety, and environmental considerations; and unattended automation in facility operations

  20. Training to raise staff awareness about safeguarding children.

    Science.gov (United States)

    Fleming, Jane

    2015-04-01

    To improve outcomes for children and young people health organisations are required to train all staff in children's safeguarding. This creates difficulties for large complex organisations where most staff provide services to the adult population. Heart of England NHS Foundation Trust is a large acute and community trust that had difficulties in engaging staff in children's safeguarding training. Compliance rates for clinical staff who were trained in children's safeguarding were low and needed to be addressed. This article sets out why safeguarding training is important for all staff and how the trust achieved staff engagement and improved compliance rates. To evaluate, maintain and develop safeguarding knowledge, understanding, skills, attitude and behaviour further resources are planned to allow access to learning resources in a variety of formats.

  1. Enhanced safeguards via solution monitoring

    International Nuclear Information System (INIS)

    Burr, T.; Wangen, L.

    1996-09-01

    Solution monitoring is defined as the essentially continuous monitoring of solution level, density, and temperature in all tanks in the process that contain, or could contain, safeguards-significant quantities of nuclear material. This report describes some of the enhancements that solution monitoring could make to international safeguards. The focus is on the quantifiable benefits of solution monitoring, but qualitatively, solution monitoring can be viewed as a form of surveillance. Quantitatively, solution monitoring can in some cases improve diversion detection probability. For example, the authors show that under certain assumptions, solution monitoring can be used to reduce the standard deviation of the annual material balance, σ MB , from approximately 17 kg to approximately 4 kg. Such reduction in σ MB will not always be possible, as they discuss. However, in all cases, solution monitoring would provide assurance that the measurement error models are adequate so that one has confidence in his estimate of σ MB . Some of the results in this report were generated using data that were simulated with prototype solution monitoring software that they are developing. An accompanying document describes that software

  2. Coordinated safeguards for materials management in a nitrate-to-oxide conversion facility

    International Nuclear Information System (INIS)

    Dayem, H.A.; Cobb, D.D.; Dietz, R.J.; Hakkila, E.A.; Kern, E.A.; Shipley, J.P.; Smith, D.B.; Bowersox, D.F.

    1977-09-01

    The conceptual design of a materials management system for safeguarding special nuclear materials in a plutonium nitrate-to-oxide conversion facility is developed and evaluated. Dynamic material balances are drawn from information provided by nondestructive-analysis techniques, process-control instrumentation, and conventional chemical analyses augmented by process-monitoring devices. Powerful statistical methods, cast in the framework of decision analysis and applied to unit-process accounting areas, ensure adequate spatial and temporal quantification of possible diversion with minimal process disruption. Modeling and simulation techniques assist in evaluating the sensitivity of the system to various diversion schemes and in comparing safeguards strategies. Features that would improve the safeguardability of the conversion process are discussed

  3. 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.

  4. Handbook of nuclear data for safeguards

    International Nuclear Information System (INIS)

    Lammer, M.; Schwerer, O.

    1991-06-01

    This handbook contains nuclear data needed by safeguards users for their work. It was initiated by an IAEA working group, and the contents were defined by the relies to a questionnaire sent to safeguards specialists. This is a preliminary edition of the handbook for distribution to safeguards and nuclear data experts for review. The present edition of the handbook contains the following basic nuclear data: actinides: nuclear decay data, thermal neutron cross sections and resonance integrals, prompt neutron data, delayed neutron data; fission products: nuclear decay data, thermal neutron capture cross sections and resonance integrals; fission product yields. Also included are appendices that summarize the data requested by safeguards users, and that present a number of questions to them and to data experts on the data contained in this preliminary issue and about additional data for possible inclusion in future editions and updates of the handbook

  5. International seminar on safeguards information reporting and processing. Extended synopses

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-12-31

    Review of the safeguards of information technology, its current developments and status of safeguards in Member States are described concerning especially the role of domestic safeguards in cooperation with IAEA Safeguards. A Number of reports is dealing with declarations provided to the IAEA pursuant to Protocols Additional to Safeguard agreements. The Information Section of the IAEA Safeguards Information Technology Division is responsible for the data entry, loading and quality control od State supplied declarations. A software system is used to process information which should be readily accessible and usable in implementation of the strengthened safeguards system. Experiences in combating illegal trafficking of nuclear materials in a number of countries are included Refs, figs, 1 tab

  6. Solution Monitoring Evaluated by Proliferation Risk Assessment and Fuzzy Optimization Analysis for Safeguards in a Reprocessing Process

    Directory of Open Access Journals (Sweden)

    Mitsutoshi Suzuki

    2013-01-01

    Full Text Available Solution monitoring (SM has been used in a nuclear reprocessing plant as an additional measure to provide assurance that the plant is operated as declared. The inline volume and density monitoring equipment with dip tubes is important for safety and safeguards purposes and is a typical example of safeguards by design (SBD. Recently safety, safeguards, and security by design (3SBD are proposed to promote an efficient and effective generation of nuclear energy. In 3SBD, proliferation risk assessment has the potential to consider likelihood of the incidence and proliferation risk in safeguards. In this study, risk assessment methodologies for safeguards and security are discussed and several mathematical methods are presented to investigate risk notion applied to intentional acts of facility misuse in an uncertainty environment. Proliferation risk analysis with the Markov model, deterrence effect with the game model, and SBD with fuzzy optimization are shown in feasibility studies to investigate the potential application of the risk and uncertainty analyses in safeguards. It is demonstrated that the SM is an effective measurement system using risk-informed and cost-effective SBD, even though there are inherent difficulties related to the possibility of operator’s falsification.

  7. Safeguards Implementation Guide for States with Small Quantities Protocols (Spanish Edition)

    International Nuclear Information System (INIS)

    2013-01-01

    The International Atomic Energy Agency (IAEA) works to enhance the contribution of nuclear energy for peace and prosperity around the world, while helping to ensure that nuclear material is not diverted to nuclear weapons or other nuclear explosive devices. In implementing safeguards, the IAEA plays an instrumental independent verification role, providing credible assurances that States' safeguards commitments are being respected. Most of the world's non-nuclear-weapon States (NNWSs) have concluded comprehensive safeguards agreements (CSAs) with the IAEA, pursuant to the Treaty on the Non- Proliferation of Nuclear Weapons (NPT). The IAEA and States are required to cooperate in the implementation of such agreements. Effective cooperation demonstrates a State's commitment to the peaceful use of nuclear energy and furthers the State's national interests by reducing the risk of unauthorized use of nuclear material. Over 100 NNWSs party to the NPT have very limited quantities of nuclear material and have concluded protocols to their CSAs which hold in abeyance many procedures in Part II of a CSA. These protocols are referred to as 'small quantities protocols' or 'SQPs' and remain in effect as long as the State meets certain eligibility criteria. The purpose of an SQP is to reduce the burden of safeguards implementation for States with little or no nuclear activities, while retaining the integrity of the safeguards system. States with SQPs have very important obligations they must fulfil under their CSAs. In 1997, as part of the IAEA's efforts to strengthen its safeguards system, the Model Additional Protocol to the Agreement(s) between State(s) and the International Atomic Energy Agency for the Application of Safeguards was developed to provide the IAEA with broader access to information and locations, thus significantly increasing the IAEA's ability to provide assurance of the absence of undeclared nuclear material and activities in States. Many States with SQPs have

  8. Safeguards Implementation Guide for States with Small Quantities Protocols (French Edition)

    International Nuclear Information System (INIS)

    2013-01-01

    The International Atomic Energy Agency (IAEA) works to enhance the contribution of nuclear energy for peace and prosperity around the world, while helping to ensure that nuclear material is not diverted to nuclear weapons or other nuclear explosive devices. In implementing safeguards, the IAEA plays an instrumental independent verification role, providing credible assurances that States' safeguards commitments are being respected. Most of the world's non-nuclear-weapon States (NNWSs) have concluded comprehensive safeguards agreements (CSAs) with the IAEA, pursuant to the Treaty on the Non- Proliferation of Nuclear Weapons (NPT). The IAEA and States are required to cooperate in the implementation of such agreements. Effective cooperation demonstrates a State's commitment to the peaceful use of nuclear energy and furthers the State's national interests by reducing the risk of unauthorized use of nuclear material. Over 100 NNWSs party to the NPT have very limited quantities of nuclear material and have concluded protocols to their CSAs which hold in abeyance many procedures in Part II of a CSA. These protocols are referred to as 'small quantities protocols' or 'SQPs' and remain in effect as long as the State meets certain eligibility criteria. The purpose of an SQP is to reduce the burden of safeguards implementation for States with little or no nuclear activities, while retaining the integrity of the safeguards system. States with SQPs have very important obligations they must fulfil under their CSAs. In 1997, as part of the IAEA's efforts to strengthen its safeguards system, the Model Additional Protocol to the Agreement(s) between State(s) and the International Atomic Energy Agency for the Application of Safeguards was developed to provide the IAEA with broader access to information and locations, thus significantly increasing the IAEA's ability to provide assurance of the absence of undeclared nuclear material and activities in States. Many States with SQPs have

  9. Ontology-based semantic information technology for safeguards: opportunities and challenges

    International Nuclear Information System (INIS)

    McDaniel, Michael

    2014-01-01

    The challenge of efficiently handling large volumes of heterogeneous information is a barrier to more effective safeguards implementation. With the emergence of new technologies for generating and collecting information this is an issue common to many industries and problem domains. Several diverse information‑intensive fields are developing and adopting ontology‑based semantic information technology solutions to address issues of information integration, federation and interoperability. Ontology, in this context, refers to the formal specification of the content, structure, and logic of knowledge within a domain of interest. Ontology‑based semantic information technologies have the potential to impact nearly every level of safeguards implementation, from information collection and integration, to personnel training and knowledge retention, to planning and analysis. However, substantial challenges remain before the full benefits of semantic technology can be realized. Perhaps the most significant challenge is the development of a nuclear fuel cycle ontology. For safeguards, existing knowledge resources such as the IAEA’s Physical Model and established upper level ontologies can be used as starting points for ontology development, but a concerted effort must be taken by the safeguards community for such an activity to be successful. This paper provides a brief background of ontologies and semantic information technology, demonstrates how these technologies are used in other areas, offers examples of how ontologies can be applied to safeguards, and discusses the challenges of developing and implementing this technology as well as a possible path forward.

  10. Transit Matching for International Safeguards

    International Nuclear Information System (INIS)

    Gilligan, K.; Whitaker, M.; Oakberg, J.

    2015-01-01

    In 2013 the U.S. Department of Energy / National Nuclear Security Administration Office of Non-proliferation and International Security (NIS) supported a study of the International Atomic Energy Agency's (IAEA) processes and procedures for ensuring that shipments of nuclear material correspond to (match) their receipts (i.e., transit matching). Under Comprehensive Safeguards Agreements, Member States are obliged to declare such information within certain time frames. Nuclear weapons states voluntarily declare such information under INFCIRC/207. This study was funded by the NIS Next Generation Safeguards Initiative (NGSI) Concepts and Approaches program. Oak Ridge National Laboratory led the research, which included collaboration with the U.S. Nuclear Regulatory Commission, the U.S. Nuclear Material Management and Safeguards System (NMMSS), and the IAEA Section for Declared Information Analysis within the Department of Safeguards. The project studied the current transit matching methodologies, identified current challenges (e.g., level of effort and timeliness), and suggested improvements. This paper presents the recommendations that resulted from the study and discussions with IAEA staff. In particular, it includes a recommendation to collaboratively develop a set of best reporting practices for nuclear weapons states under INFCIRC/207. (author)

  11. Societal risk approach to safeguards design and evaluation

    International Nuclear Information System (INIS)

    Murphey, W.M.; Sherr, T.S.; Bennett, C.A.

    1975-01-01

    A comprehensive rationale for safeguards design and evaluation, and a framework for continuing systematic assessment of the system's effectiveness and efficient allocation of available safeguards resources for balanced protection, were developed. The societal risk approach employed considers the likelihood of successful destructive acts involving nuclear materials or facilities and the magnitude of the effects on society. The safeguards problem is described in terms of events affecting societal risk and adversary actions. Structure of the safeguards system and the evaluation of its adequacy are discussed. Adversary characteristics are also discussed

  12. Comprehensive safeguards evaluation methods and societal risk analysis

    International Nuclear Information System (INIS)

    Richardson, J.M.

    1982-03-01

    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. Use of fuel reprocessing plant instrumentation for international safeguards

    International Nuclear Information System (INIS)

    Ayers, A.L.

    1977-01-01

    The International Atomic Energy Agency has a program for developing instrumentation to be used by safeguards inspectors at reprocessing facilities. These instruments have generally been individual pieces of equipment for improving the accuracy of existing measurement instrumentation or equipment to perform nondestructive assay on a selected basis. It is proposed that greater use be made of redundant plant instrumentation and data recovery systems that could augment plant instrumentation to verify the validity of plant measurements. Use of these methods for verfication must be proven as part of an operating plant before they can be relied upon for safeguards surveillance. Inspectors must be qualified in plant operations, or have ready access to those so qualified, if the integrity of the operation is to be properly assessed. There is an immediate need for the development and in-plant proof testing of an integrated gamma, passive neutron, and active neutron measurement system for drum quantities of radioactive trash. The primary safeguards effort should be limited to plutonium and highly enriched uranium

  14. Safeguards at NRC licensed facilities: Are we doing enough

    International Nuclear Information System (INIS)

    Asselstine, J.K.

    1986-01-01

    The Nuclear Regulatory Commission is pursuing a number of initiatives in the safeguards area. The Commission is conducting a reassessment of its safeguards design basis threat statements to consider the possible implications of an explosive-laden vehicle for U.S. nuclear safeguards and to examine the comparability of safeguards features at NRC-licensed and DOE facilities. The Commission is also completing action on measures to protect against the sabotage threat from an insider at NRC-licensed facilities, and is examining the potential safety implications of safeguards measures. Finally, the NRC has developed measures to reduce the theft potential for high-enriched uranium

  15. International safeguards for critical facilities

    International Nuclear Information System (INIS)

    Ney, J.F.; Todd, J.L.

    1979-01-01

    A study was undertaken to investigate various approaches to provide international safeguards for critical facilities and to select an optimized system. Only high-inventory critical facilities were considered. The goal of the study was to detect and confirm the protracted or abrupt diversion of 8kg of plutonium or 25kg of the uranium isotope 235 within approximately a week of the diversion. The general safeguards alternatives considered were (1) continuous inspections by resident inspectors, with varying degrees of comprehensiveness, (2) periodic inspections by regional inspectors at varying time intervals, (3) unattended containment/surveillance measures, and (4) various combinations of the above. It was concluded that a practical and effective international safeguards system can be achieved by employing a method of continuously monitoring facility activities which could lead to diversion. This is in addition to the routine inspections typical of current international safeguards. Monitoring detects inventory discrepancies and violations of agreed-upon procedural restrictions, as well as unauthorized removal of Special Nuclear Materials (SNM). A special inventory is used following detection to confirm any suspected diversion. Comparison of 28 safeguards options led to the selection of a system for further development which uses a combination of surveillance and inspection by resident IAEA personnel, containment/surveillance by unattended equipment, and routine inventory sampling. A development programme is described which is intended to demonstrate the feasibility of several containment and surveillance measures proposed in the study. Included are a personnel portal and an instrument/material pass-through as well as associated recording and tamper-protection features. (author)

  16. Safeguards Summary Event List (SSEL)

    International Nuclear Information System (INIS)

    1983-02-01

    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

  17. Safeguards Summary Event List (SSEL)

    International Nuclear Information System (INIS)

    1982-07-01

    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

  18. International safeguards: experience and prospects

    International Nuclear Information System (INIS)

    Keepin, G.R.; Menlove, H.O.

    1982-01-01

    IAEA safeguards have been applied to over 95% of the nuclear material and facilities outside of the nuclear weapon states. The present system of nonproliferation agreements implemented by IAEA safeguards likely will not be changed in the foreseeable future. Instruments used for nondestructive analysis are described: portable multichannel analyzer, high-level neutron coincidence counter, active well coincidence counter, and neutron coincidence collar. 7 figs

  19. Organizational Culture, 3S, and Safeguards by Design

    Energy Technology Data Exchange (ETDEWEB)

    Mladineo, Stephen V.; Frazar, Sarah L.

    2012-01-31

    While Safety and Security Culture are well socialized among nuclear facility designers, the concept of safeguards culture is less well defined. One area where safeguards culture may play a helpful role is in the area of Safeguards by Design. This paper will include a theoretical discussion of organizational culture, leading with safety culture and security culture that are well known, and positing that there may be room to think about safeguards culture along with the others. It will also examine the utility of the 3S concept and how this concept has been used in training for newcomer states. These will lead into a discussion of how the addition of safeguards to the mix of safety by design and security by design can be valuable, particularly as it is socialized to newcomer states.

  20. Light water reactor safeguards system evaluation

    International Nuclear Information System (INIS)

    Varnado, G.B.; Ericson, D.M. Jr.; Bennett, H.A.; Hulme, B.L.; Daniel, S.L.

    1978-01-01

    A methodology for assessing the effectiveness of safeguards systems was developed in this study and was applied to a typical light water reactor plant. The relative importance of detection systems, barriers, response forces and other safeguards system components was examined in extensive parameter variation studies. (author)

  1. 21 CFR 312.88 - Safeguards for patient safety.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 5 2010-04-01 2010-04-01 false Safeguards for patient safety. 312.88 Section 312... Severely-debilitating Illnesses § 312.88 Safeguards for patient safety. All of the safeguards incorporated within parts 50, 56, 312, 314, and 600 of this chapter designed to ensure the safety of clinical testing...

  2. Report Of The Workshop On Nuclear Facility Design Information Examination And Verification For Safeguards

    International Nuclear Information System (INIS)

    Metcalf, Richard; Bean, Robert

    2009-01-01

    . Consequently, the NNSA Office of International Regimes and Agreements (NA-243) sponsored a team of U.S. Department of Energy National Laboratory nuclear safeguards experts and technologists to conduct a workshop on methods and technologies for improving this activity, under the ASA-100 Advanced Safeguards Approaches Project. The workshop focused on reviewing and discussing the fundamental safeguards needs, and presented technology and/or methods that could potentially address those needs more effectively and efficiently. Conclusions and Recommendations for technology to enhance the performance of DIV inspections are presented by the workshop team.

  3. Game theoretical analysis of safeguards effectiveness. Pt. 3

    International Nuclear Information System (INIS)

    Avenhaus, R.; Canty, M.J.

    1989-12-01

    In Part 1 of the present study on safeguards effectiveness it was shown that for attribute sampling problems the guaranteed probability of detection can be used as a measure for the effectiveness of safeguards procedures. In Part 2 this measure was used for variable sampling problems, with given false alarm probabilities as boundary conditions. In Part 3 we show that the measure can be justified by appropriate game theoretical models. Furthermore, we show that, for attribute sampling, the equilibrium strategy of the operator is legal behavior if appropriate effort conditions are fulfilled, whether or not the inspector announces his strategy in advance. For variable sampling, legal behavior is equilibrium strategy of the operator only if the inspector announces his strategy. (orig.)

  4. 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.

  5. Human-Centred Computing for Assisting Nuclear Safeguards

    International Nuclear Information System (INIS)

    Szoke, I.

    2015-01-01

    With the rapid evolution of enabling hardware and software, technologies including 3D simulation, virtual reality (VR), augmented reality (AR), advanced user interfaces (UI), and geographical information systems (GIS) are increasingly employed in many aspects of modern life. In line with this, the nuclear industry is rapidly adopting emerging technologies to improve efficiency and safety by supporting planning and optimization of maintenance and decommissioning work, as well as for knowledge management, surveillance, training and briefing field operatives, education, etc. For many years, the authors have been involved in research and development (R&D) into the application of 3D simulation, VR, and AR, for mobile, desktop, and immersive 3D systems, to provide a greater sense of presence and situation awareness, for training, briefing, and in situ work by field operators. This work has resulted in a unique software base and experience (documented in numerous reports) from evaluating the effects of the design of training programmes and briefing sessions on human performance and training efficiency when applying various emerging technologies. In addition, the authors are involved in R&D into the use of 3D simulation, advanced UIs, mobile computing, and GIS systems to support realistic visualization of the combined radiological and geographical environment, as well as acquisition, analyzes, visualization and sharing of radiological and other data, within nuclear installations and their surroundings. The toolkit developed by the authors, and the associated knowledge base, has been successfully applied to various aspects of the nuclear industry, and has great potential within the safeguards domain. It can be used to train safeguards inspectors, brief inspectors before inspections, assist inspectors in situ (data registration, analyzes, and communication), support the design and verification of safeguards systems, conserve data and experience, educate future safeguards

  6. The UK safeguards R and D support program

    International Nuclear Information System (INIS)

    Patrick, B.H.; Andrew, G.; Tuley, J.N.

    1991-01-01

    The UK Safeguards R and D Programme in support of IAEA safeguards was formally initiated in 1981. Funding is provided by HM Government through the Department of Energy, responsibility for managing and carrying out the work being placed in the hands of the UK Atomic Energy Authority The programme covers safeguards in a variety of areas, including reprocessing and enrichment plants, nuclear materials in waste, authentication of facility computer systems, training courses for safeguards inspectors, containment and surveillance, destructive and non-destructive assay techniques and techniques for assessing diversion path analysis. In this paper an overview of the work is presented

  7. Applying new safeguards technology to existing nuclear facilities

    International Nuclear Information System (INIS)

    Harris, W.J.; Wagner, E.P.

    1979-01-01

    The application and operation of safeguards instrumentation in a facility containing special nuclear material is most successful when the installation is desinged for the operation of the specific facility. Experience at the Idaho National Engineering Laboratory demonstrates that installation designs must consider both safeguards and production requirements of specific facilities. Equipment selection and installation design influenced by the training and experience of production operations and safeguards personnel at a specific facility help assure successful installation, reliable operation, and minimal operator training. This minimizes impacts on existing plant production activities while maximizing utility of the safeguards information obtained

  8. Applying new safeguards technology to existing nuclear facilities

    International Nuclear Information System (INIS)

    Johnson, C.E.; Wagner, E.P.

    1979-01-01

    The application and operation of safeguards instrumentation in a facility containing special nuclear material is most successful when the installation is designed for the operation of the specific facility. Experience at the Idaho National Engineering Laboratory demonstrates that installation designs must consider both Safeguards and Production requirements of specific facilities. Equipment selection and installation design influenced by the training and experience of production operations and safeguards personnel at a specific facility help assure successful installation, reliable operation, and minimal operator training. This minimizes impacts on existing plant production activities while maximizing utility of the safeguards information obtained

  9. Paying tribute to 25 years of safeguards leadership

    International Nuclear Information System (INIS)

    1994-01-01

    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

  10. Symposium on international safeguards: Addressing verification challenges. Book of extended synopses

    International Nuclear Information System (INIS)

    2006-01-01

    A safeguards symposium has traditionally been organized by the Safeguards Department approximately every four years. The 2006 symposium addresses challenges to IAEA safeguards that have emerged or grown more serious since 2001. The increase in size and flexibility of uranium enrichment plants, for instance, and the spread of enrichment technology to a wider circle of States, pose challenges to traditional safeguards approaches. The procurement and supply networks discovered in 2004, dealing in sensitive nuclear technology and information, have serious implications for the future effectiveness of IAEA safeguards. The symposium will provide an opportunity for the IAEA and Member States to discuss options for dealing constructively with trade in sensitive nuclear technology. Reflecting developments since 2001, the 2006 symposium will focus on current challenges to the safeguards system, improving collection and analysis of safeguards information (analysis, processing tools, satellite imagery), advances in safeguards techniques and technology (future technology, neutron techniques, spent fuel verification, reprocessing, environmental sampling, containment and surveillance), further strengthening safeguards practices and approaches (safeguards approaches, integrated safeguards, R/SSAC, destructive analysis, non-destructive analysis, enrichment, reprocessing, spent fuel transfer) and future challenges. This publication contains 183 extended synopses, each of them was indexed separately

  11. Symposium on international safeguards: Addressing verification challenges. Book of extended synopses

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    A safeguards symposium has traditionally been organized by the Safeguards Department approximately every four years. The 2006 symposium addresses challenges to IAEA safeguards that have emerged or grown more serious since 2001. The increase in size and flexibility of uranium enrichment plants, for instance, and the spread of enrichment technology to a wider circle of States, pose challenges to traditional safeguards approaches. The procurement and supply networks discovered in 2004, dealing in sensitive nuclear technology and information, have serious implications for the future effectiveness of IAEA safeguards. The symposium will provide an opportunity for the IAEA and Member States to discuss options for dealing constructively with trade in sensitive nuclear technology. Reflecting developments since 2001, the 2006 symposium will focus on current challenges to the safeguards system, improving collection and analysis of safeguards information (analysis, processing tools, satellite imagery), advances in safeguards techniques and technology (future technology, neutron techniques, spent fuel verification, reprocessing, environmental sampling, containment and surveillance), further strengthening safeguards practices and approaches (safeguards approaches, integrated safeguards, R/SSAC, destructive analysis, non-destructive analysis, enrichment, reprocessing, spent fuel transfer) and future challenges. This publication contains 183 extended synopses, each of them was indexed separately.

  12. Safeguards Summary Event List (SSEL)

    International Nuclear Information System (INIS)

    1984-03-01

    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

  13. Safeguards through secure automated fabrication

    International Nuclear Information System (INIS)

    DeMerschman, A.W.; Carlson, R.L.

    1982-01-01

    Westinghouse Hanford Company, a prime contractor for the U.S. Department of Energy, is constructing the Secure Automated Fabrication (SAF) line for fabrication of mixed oxide breeder fuel pins. Fuel processing by automation, which provides a separation of personnel from fuel handling, will provide a means whereby advanced safeguards concepts will be introduced. Remote operations and the inter-tie between the process computer and the safeguards computer are discussed

  14. Safeguarding of large scale reprocessing and MOX plants

    International Nuclear Information System (INIS)

    Howsley, R.; Burrows, B.; Longevialle, H. de; Kuroi, H.; Izumi, A.

    1997-01-01

    In May 97, the IAEA Board of Governors approved the final measures of the ''93+2'' safeguards strengthening programme, thus improving the international non-proliferation regime by enhancing the effectiveness and efficiency of safeguards verification. These enhancements are not however, a revolution in current practices, but rather an important step in the continuous evolution of the safeguards system. The principles embodied in 93+2, for broader access to information and increased physical access already apply, in a pragmatic way, to large scale reprocessing and MOX fabrication plants. In these plants, qualitative measures and process monitoring play an important role in addition to accountancy and material balance evaluations in attaining the safeguard's goals. This paper will reflect on the safeguards approaches adopted for these large bulk handling facilities and draw analogies, conclusions and lessons for the forthcoming implementation of the 93+2 Programme. (author)

  15. Effectiveness evaluation of alternative fixed-site safeguard security systems

    International Nuclear Information System (INIS)

    Chapman, L.D.

    1976-01-01

    An evaluation of a fixed-site physical protection system must consider the interrelationships of barriers, alarms, on-site and off-site guards, and their effectiveness against a forcible adversary attack intent on creating an act of sabotage of theft. A computer model, Forcible Entry Safeguard Effectiveness Model (FESEM), was developed for the evaluation of alternative fixed-site protection systems. It was written in the GASP IV simulation language. A hypothetical fixed-state protection system is defined and relative evaluations from a cost-effectiveness point of view are presented in order to demonstrate how the model can be used. Trade-offs involving on-site and off-site response forces and response times, perimeter system alarms, barrier configurations, and varying levels of threat are analyzed. The computer model provides a framework for performing inexpensive experiments on fixed-site security systems, for testing alternative decisions, and for determining the relative cost effectiveness associated with these decision policies

  16. 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 a...

  17. Euratom Safeguards: Improving Safeguards by Cooperation in R&D and Implementation

    International Nuclear Information System (INIS)

    Schwalbach, P.; Schoop, K.; Ancius, D.; Marszalek, Y.; Smejkal, A.; Vaccaro, S.; De Baere, P.; Koutsoyannopoulos, C.; Meylemans, P.; Murtezi, M.; Persson, L.; Synetos, S.; Tempesta, S.; Canadell Bofarull, V.; Turner, D.; Goncalves, J.G.M.; Peerani, P.; Berndt, R.; Stringa, E.; Richir, P.; Sequeira, V.; Tagziria, H.; Janssens, W.A.M.; Zuleger, E.; Luetzenkirchen, K.; )

    2015-01-01

    Euratom Safeguards, implemented on the basis of the Euratom Treaty by the European Commission's Directorate Nuclear Safeguards, is the largest Regional Safeguards System and involved in many R&D activities of its own, often in close cooperation with external partners. Most of the results of these activities are shared with or offered to the IAEA. The work described in this paper is complementary to the projects run by the European Commission Cooperative Support Programme (ECSP) to the IAEA. The ECSP activities will be described elsewhere at this conference. The present paper will provide an overview on R&D activities run in addition to the ECSP, and will attempt to link them to the capabilities discussed by the IAEA in the Long Term R&D Plan. The range of topics will include work on unattended data acquisition systems (hard- and software), advanced data analysis tools, news from seals related technology, containment and design verification applications of 3D lasers, activities to keep standard measurement technologies sustainable etc. Work done with the IAEA in preparation of new facilities and facility types will be discussed briefly. The paper will also highlight some current challenges and make suggestions how to address them. (author)

  18. 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.

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

    International Nuclear Information System (INIS)

    Sapir, J.L.

    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 present status of IAEA safeguards on nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    1979-02-01

    This paper examines the present approach of the International Atomic Energy Agency (IAEA) to safeguarding various types of facilities in the nuclear fuel cycle, in the hope that it will serve as useful background material for several of the various working groups of the International Nuclear Fuel Cycle Evaluation (INFCE). The objectives and criteria of safeguards as well as the specific safeguards techniques which are utilized by the Agency, are addressed. In Part I, a general overview of safeguards as well as a discussion of procedures applicable to most if not all IAEA safeguarded facilities are included. Part II is broken down into specific facility types and focusses on the particular safeguards measures applied to them. Safeguards have reached different degrees of development for different types of facilities, in part because the Agency's experience in safeguarding certain types is considerably greater than for other types. Thus the Agency safeguards described herein are not static, but are continuously evolving. This evolution results not only from the fact that larger and more complex facilities have been coming under safeguards. Changes are also continually being introduced based on practical experience and research and development aimed at improving safeguards efficiency, reducing intrusiveness into plant operations, minimizing operator and inspector radiation exposure, and reducing subjective evaluations in determining the effectiveness of safeguards. To these ends, the technical support programmes of various countries are playing an important role. It is emphasized that this paper is not intended to evaluate the effectiveness of Agency safeguards or to highlight problem areas. It is simply aimed at providing a picture of what safeguards are or are planned to be at various stages of the fuel cycle

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

    International Nuclear Information System (INIS)

    Kerr, H.T.; Ehinger, M.H.; Wachter, J.W.; Hebble, T.L.

    1986-10-01

    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 implications of laser isotope separation

    International Nuclear Information System (INIS)

    Moriarty, T.F.; Taylor, K.

    1993-10-01

    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)

  3. Recent developments in the implementation of Euratom safeguards

    International Nuclear Information System (INIS)

    Gmelin, W.; Bommelle, P.; Sharpe, B.W.; Love, B.

    1983-01-01

    The EURATOM safeguards system is based legally on the 1958 Treaty of Rome establishing the original Community of six (now 10) countries. Under this safeguards system, the Commission has, inter alia, ''to satisfy itself that any particular safeguarding obligations assumed by the Community under an agreement concluded with a third state or an international organisation are complied with'' (art. 77b). The practical implementation of safeguards within the Community is significantly influenced by the requirements of: (a) the three different agreements between the Community, its Member States and the IAEA, concerning the application of IAEA safeguards to some or all of the civil nuclear materials in the Community, and (b) the various agreements between the Community and certain third countries, concerning inter alia the application of safeguards within the Community to nuclear materials supplied, directly or indirectly, by these third countries. Within the past four years significant developments have occurred in both groups of agreements. The EURATOM safeguards organisation is the only multinational safeguards organisation in the world, and currently has a staff of some 120 inspectors, with appropriate administrative support, and can draw for research and development work on the resources of the Community's Joint Research Centre. The recent changes in inspection techniques, particularly in relation to non-destructive assay techniques, and the implementation of containment and surveillance measures, are discussed. A description is given of the experience gained in recent years in the operation of ''Joint Teams'' of EURATOM and IAEA inspectors in certain plants as well as the continuing experience gained under the normal regime, using the observation principle, as foreseen in the respective Agreement

  4. A technical analysis of the IAEA nuclear safeguards

    International Nuclear Information System (INIS)

    Yoon, J. W.

    1998-01-01

    In the post-Cold War era, the threats of horizontal nuclear proliferation emerge as the forefront security issue while the nuclear arms races among existing nuclear weapon states reduce to a remarkable extent. In this context, there arises lots of research attention to the IAEA nuclear safeguards which have been viewed as the core of international monitoring on the clandestine nuclear activities of potential proliferators. However, previous attention tended to highlight the political aspects of the IAEA nuclear safeguards, centering on the possibilities and limitations of the IAEA's inspection authority. In contrast, this paper purports to focus on the technical aspects of the IAEA nuclear safeguards, so it can show the intrinsic problems of those safeguards in stemming the proliferation of nuclear weapons. This paper mainly deals with the technical objectives and options of the IAEA nuclear safeguards, the technical indices of clandestine nuclear activities, and some measures to improve the efficacy of the IAEA nuclear safeguards. Hopefully, this paper is expected to lead us to approach the issue of the North Korean nuclear transparency from the technical perspective as well as the political one

  5. THIEF: An interactive simulation of nuclear materials safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Stanbro, W. D.

    1990-01-01

    The safeguards community is facing an era in which it will be called upon to tighten protection of nuclear material. At the same time, it is probable that safeguards will face more competition for available resources from other activities such as environmental cleanup. To exist in this era, it will be necessary to understand and coordinate all aspects of the safeguards system. Because of the complexity of the interactions involved, this process puts a severe burden on designers and operators of safeguards systems. This paper presents a simulation tool developed at the Los Alamos National Laboratory to allow users to examine the interactions among safeguards elements as they apply to combating the insider threat. The tool consists of a microcomputer-based simulation in which the user takes the role of the insider trying to remove nuclear material from a facility. The safeguards system is run by the computer and consists of both physical protection and MC A computer elements. All data elements describing a scenario can be altered by the user. The program can aid in training, as well as in developing threat scenarios. 4 refs.

  6. Summary of safeguards interactions between Los Alamos and Chinese scientists

    International Nuclear Information System (INIS)

    Eccleston, G.W.

    1994-01-01

    Los Alamos has been collaborating since 1984 with scientists from the Chinese Institute of Atomic Energy (CIAE) to develop nuclear measurement instrumentation and safeguards systems technologies that will help China support implementation of the nonproliferation treaty (NPT). To date, four Chinese scientists have visited Los Alamos, for periods of six months to two years, where they have studied nondestructive assay instrumentation and learned about safeguards systems and inspection techniques that are used by International Atomic Energy Agency (IAEA) inspectors. Part of this collaboration involves invitations from the CIAE to US personnel to visit China and interact with a larger number of Institute staff and to provide a series of presentations on safeguards to a wider audience. Typically, CIAE scientists, Beijing Institute of Nuclear Engineering (BINE) staff, and officials from the Government Safeguards Office attend the lectures. The BINE has an important role in developing the civilian nuclear power fuel cycle. BINE is designing a reprocessing plant for spent nuclear fuel from Chinese nuclear Power reactors. China signed the nonproliferation treaty in 1992 and is significantly expanding its safeguards expertise and activities. This paper describes the following: DOE support for US and Chinese interactions on safeguards; Chinese safeguards; impacts of US-China safeguards interactions; and possible future safeguards interactions

  7. University of Texas Safeguards by Design Problem Statement

    Energy Technology Data Exchange (ETDEWEB)

    Rauch, Eric Benton [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Scherer, Carolynn P. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Ruggiero, Christy E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2018-01-22

    This document describes the problem statement that students at the University of Texas will use for their senior level capstone design class. The purpose of this project is to introduce students to Safeguards by Design concepts as part of their capstone design course at the culmination of their degree program. This work is supported by Los Alamos National Laboratory with FY17 and FY18 programmatic funding from the U. S. Department of Energy’s (DOE) National Nuclear Security Administration (NNSA), through the Office of Defense Nuclear Nonproliferation (DNN), Office of International Nuclear Safeguards (INS), Next Generation Safeguards Initiative (NGSI), Human Resource Development Program, Safeguards by Design Project.

  8. Elementary survey of nuclear safeguards problems

    International Nuclear Information System (INIS)

    Tobias, M.L.

    1975-01-01

    The discussion presented on nuclear safeguards is confined primarily to the subject of safeguards for fixed sites. The legal and quasi-legal requirements are briefly outlined. Preventive measures against theft, terrorism, sabotage, or irrational acts by employees and against sabotage by armed gangs are the aspects emphasized. Some of the cost aspects are indicated

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

    International Nuclear Information System (INIS)

    1979-01-01

    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. Oak Ridge National Laboratory Next Generation Safeguards Initiative

    Energy Technology Data Exchange (ETDEWEB)

    Kirk, Bernadette Lugue [ORNL; Eipeldauer, Mary D [ORNL; Whitaker, J Michael [ORNL

    2011-12-01

    In 2007, the Department of Energy's National Nuclear Security Administration (DOE/NNSA) Office of Nonproliferation and International Security (NA-24) completed a comprehensive review of the current and potential future challenges facing the international safeguards system. The review examined trends and events impacting the mission of international safeguards and the implications of expanding and evolving mission requirements on the legal authorities and institutions that serve as the foundation of the international safeguards system, as well as the technological, financial, and human resources required for effective safeguards implementation. The review's findings and recommendations were summarized in the report, 'International Safeguards: Challenges and Opportunities for the 21st Century (October 2007)'. One of the report's key recommendations was for DOE/NNSA to launch a major new program to revitalize the international safeguards technology and human resource base. In 2007, at the International Atomic Energy Agency's General Conference, then Secretary of Energy Samuel W. Bodman announced the newly created Next Generation Safeguards Initiative (NGSI). NGSI consists of five program elements: (1) Policy development and outreach; (2) Concepts and approaches; (3) Technology and analytical methodologies; (4) Human resource development; and (5) Infrastructure development. The ensuing report addresses the 'Human Resource Development (HRD)' component of NGSI. The goal of the HRD as defined in the NNSA Program Plan (November 2008) is 'to revitalize and expand the international safeguards human capital base by attracting and training a new generation of talent.' One of the major objectives listed in the HRD goal includes education and training, outreach to universities, professional societies, postdoctoral appointments, and summer internships at national laboratories. ORNL is a participant in the NGSI program, together

  11. India and the nuclear safeguards controversy

    International Nuclear Information System (INIS)

    Poulose, T.T.

    1979-01-01

    A brief account of the origin and development of the safeguards system to prevent diversion of nuclear material from its peaceful uses to production of nuclear explosives is given. India is firmly opposed to the discriminatory characteristics of the system. The IAEA safeguards apply to those nations (most of them developing nations) seeking Agency aid and not to the nuclear weapons powers and other advanced nuclear powers who do not need Agency aid. Even though the Tarapur Agreement does not provide for full scope safeguards, U.S.A., particularly after 1974 Pokharan explosion, is pressurisinq India to accept them by delaying the supply of enriched uranium for the Tarapur Power Plant. As is assumed by the Americans, India is not indifferent to the problem of proliferation. On the other hand, it has renounced nuclear weapons as an instrument of national policy and is committed to non-proliferation. India has all along since independence advocated universal and non-discriminating full scope safeguards system applicable to all nations, both nuclear and non-nuclear powers and to all nuclear facilities. (M.G.B.)

  12. Remote monitoring: A global partnership for safeguards

    International Nuclear Information System (INIS)

    Bardsley, J.

    1996-01-01

    With increased awareness of the significant changes of the past several years and their effect on the expectations to international safeguards, it is necessary to reflect on the direction for development of nuclear safeguards in a new era and the resulting implications. The time proven monitoring techniques, based on quantitative factors and demonstrated universal application, have shown their merit. However, the new expectations suggest a possibility that a future IAEA safeguards system could rely more heavily on the value of a comprehensive, transparent, and open implementation regime. With the establishment of such a regime, it is highly likely that remote monitoring will play a significant role. Several states have seen value in cooperating with each other to address the many problems associated with the remote interrogation of integrated monitoring systems. As a consequence the International Remote Monitoring Project was organized to examine the future of remote monitoring in International Safeguards. This paper provides an update on the technical issues, the future plans, and the safeguards implications of cooperative programs relating to remote monitoring. Without providing answers to the policy questions involved, it suggests that it is timely to begin addressing these issues

  13. Protecting safeguards information / Division of technical support

    International Nuclear Information System (INIS)

    2002-01-01

    This DVD contains two films representing the key aspects of the IAEA Department of Safeguards. 'Protecting Safeguards Information' is a narrative/fiction film which presents the Agency's information handling and protection measures. A security representative from a fictional nation receives a briefing on the procedures and methods used by the Department. These techniques will assure member states that the information they provide to the Agency is kept safe and confidential. 'Division of Technical Support' is a non-fiction documentary which presents a detailed look at the technical capabilities and management techniques used by the Agency in nuclear material accountancy. The film covers many aspects of safeguards equipment and techniques including: NDA and DA instruments, seals, surveillance, training, development and maintenance. Taken together, these films provide an introduction and overview to many important aspects of the IAEA Department of Safeguards. (IAEA)

  14. Real‑time, fast neutron detection for stimulated safeguards assay

    International Nuclear Information System (INIS)

    Joyce, Malcolm J.; Adamczyk, Justyna; Plenteda, Romano; Aspinall, Michael D.; Cave, Francis D.

    2015-01-01

    The advent of low‑hazard organic liquid scintillation detectors and real‑time pulse‑shape discrimination (PSD) processing has suggested a variety of modalities by which fast neutrons, as opposed to neutrons moderated prior to detection, can be used directly to benefit safeguards needs. In this paper we describe a development of a fast‑neutron based safeguards assay system designed for the assessment of 235 U content in fresh fuel. The system benefits from real‑time pulse‑shape discrimination processing and auto‑calibration of the detector system parameters to ensure a rapid and effective set‑up protocol. These requirements are essential in optimising the speed and limit of detection of the fast neutron technique, whilst minimising the intervention needed to perform the assay.

  15. Safeguarding research reactors

    International Nuclear Information System (INIS)

    Powers, J.A.

    1983-03-01

    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

  16. The Safeguards Active Response Inventory System (SARIS)

    International Nuclear Information System (INIS)

    Carlson, R.L.

    1985-04-01

    The Safeguards Active Response Inventory System (SARIS) was developed by Westinghouse Hanford Company (WHC) to perform material control and accountability on all the nuclear material under WHC's jurisdiction. SARIS has been in operation for four and one-half years. It has reduced physical inventory plant shutdown time from several days to a few hours. The user-friendly interface has proven successful, as the training time for a new operator is only two to three hours; also errors have been dramatically reduced. The modeling features of SARIS have reduced the reported inventory difference and provide better information for measurement of scrap and waste. The audit files have been usefull in resolving data entry errors and the backup features have averted several potential problems. SARIS as a computerized accountability system has replaced manual record keeping with a consequent increase in productivity. 4 refs

  17. Fibre optic networks for safeguards applications

    International Nuclear Information System (INIS)

    Smith, B.G.R.; Chare, P.; Barrier, A.

    1991-01-01

    The Euratom Safeguards Directorate has recently installed a fibre optic network in a new large scale nuclear facility in the European Communities. The selection, installation and commissioning of the fibre optic network is discussed from the viewpoint of network topology, physical testing, trouble shooting and authentication. The future use of fibre optic networks for safeguards applications is discussed

  18. LESSONS LEARNED IN TESTING OF SAFEGUARDS EQUIPMENT

    International Nuclear Information System (INIS)

    Pepper, S.; Farnitano, M.; Carelli, J.; Hazeltine, J.; Bailey, D.

    2001-01-01

    The International Atomic Energy Agency's (IAEA) Department of Safeguards uses complex instrumentation for the application of safeguards at nuclear facilities around the world. Often, this equipment is developed through cooperation with member state support programs because the Agency's requirements are unique and are not met by commercially available equipment. Before approving an instrument or system for routine inspection use, the IAEA subjects it to a series of tests designed to evaluate its reliability. In 2000, the IAEA began to observe operational failures in digital surveillance systems. In response to the observed failures, the IAEA worked with the equipment designer and manufacturer to determine the cause of failure. An action plan was developed to correct the performance issues and further test the systems to make sure that additional operational issues would not surface later. This paper addresses the steps taken to address operation issues related to digital image surveillance systems and the lessons learned during this process

  19. REPORT OF THE WORKSHOP ON NUCLEAR FACILITY DESIGN INFORMATION EXAMINATION AND VERIFICATION FOR SAFEGUARDS

    Energy Technology Data Exchange (ETDEWEB)

    Richard Metcalf; Robert Bean

    2009-10-01

    in the future. Consequently, the NNSA Office of International Regimes and Agreements (NA-243) sponsored a team of U.S. Department of Energy National Laboratory nuclear safeguards experts and technologists to conduct a workshop on methods and technologies for improving this activity, under the ASA-100 Advanced Safeguards Approaches Project. The workshop focused on reviewing and discussing the fundamental safeguards needs, and presented technology and/or methods that could potentially address those needs more effectively and efficiently. Conclusions and Recommendations for technology to enhance the performance of DIV inspections are presented by the workshop team.

  20. Safeguards against use of nuclear material for weapons

    International Nuclear Information System (INIS)

    Sanders, B.; Rometsch, R.

    1975-01-01

    The history of safeguards is traced from the first session of the United Nations Atomic Energy Commission in 1946, through the various stages of the IAEA safeguard system for nuclear materials and to the initiation of the Treaty on the Non-proliferation of Nuclear Weapons in 1968. The role of the IAEA under the treaty is discussed. The structure and content of safeguards agreements in connection with the treaty were laid down and the objective of safeguards clearly defined. The methods of verification by the IAEA of the facility operator's material accountancy through inspection and statistical analysis and evaluation of 'material unaccounted for' are explained. The extent to which the IAEA may make use of the State's system of accounting and control of nuclear materials is considered. Reference is also made to the question of protection against theft and sabotage. Finally the scope of safeguards work for the next 15 years is forecast. (U.K.)