The process monitoring computer system an integrated operations and safeguards surveillance system

International Nuclear Information System (INIS)

Liester, N.A.

1995-01-01

The use of the Process Monitoring Computer System (PMCS) at the Idaho Chemical Processing Plant (ICPP) relating to Operations and Safeguards concerns is discussed. Measures taken to assure the reliability of the system data are outlined along with the measures taken to assure the continuous availability of that data for use within the ICPP. The integration of process and safeguards information for use by the differing organizations is discussed. The PMCS successfully demonstrates the idea of remote Safeguards surveillance and the need for sharing of common information between different support organizations in an operating plant

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.

Using Process Load Cell Information for IAEA Safeguards at Enrichment Plants

International Nuclear Information System (INIS)

Laughter, Mark D.; Whitaker, J. Michael; Howell, John

2010-01-01

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

Advances in the Processing of VHR Optical Imagery in Support of Safeguards Verification

International Nuclear Information System (INIS)

Niemeyer, I.; Listner, C.; Canty, M.

2015-01-01

Under the Additional Protocol of the Non-Proliferation Treaty (NPT) complementing the safeguards agreements between States and the International Atomic Energy Agency, commercial satellite imagery, preferably acquired by very high-resolution (VHR) satellite sensors, is an important source of safeguards-relevant information. Satellite imagery can assist in the evaluation of site declarations, design information verification, the detection of undeclared nuclear facilities, and the preparation of inspections or other visits. With the IAEA's Geospatial Exploitation System (GES), satellite imagery and other geospatial information such as site plans of nuclear facilities are available for a broad range of inspectors, analysts and country officers. The demand for spatial information and new tools to analyze this data is growing, together with the rising number of nuclear facilities under safeguards worldwide. Automated computer-driven processing of satellite imagery could therefore add a big value in the safeguards verification process. These could be, for example, satellite imagery pre-processing algorithms specially developed for new sensors, tools for pixel or object-based image analysis, or geoprocessing tools that generate additional safeguards-relevant information. In the last decade procedures for automated (pre-) processing of satellite imagery have considerably evolved. This paper aims at testing some pixel-based and object-based procedures for automated change detection and classification in support of safeguards verification. Taking different nuclear sites as examples, these methods will be evaluated and compared with regard to their suitability to (semi-) automatically extract safeguards-relevant information. (author)

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

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

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

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)

The European experience in safeguarding nuclear fuel recycle processes and Pu stores

International Nuclear Information System (INIS)

Synetos, Sotiris

2013-01-01

Civil nuclear programs in the European Union member states have from their onset included fuel recycling as an option. The EURATOM Treaty gives to the European Commission the obligation to apply safeguards controls to all civil Nuclear Material in the European Union, and to facilitate the implementation of IAEA safeguards. The European Commission (EURATOM) has thus gained years of experience in safeguarding reprocessing plants, Pu storages, and MOX fuel fabrication plants and is currently participating in the development of approaches and measures for safeguarding long term repositories. The aim of this paper is to present the regulator's views and experience on safeguarding nuclear fuel recycle processes and Pu stores, which is based on the following principles: -) Early involvement of the control organizations in the design of the safeguards measures to be developed for a plant (currently referred to as Safeguards by Design); -) Early definition of a safeguards strategy including key measurement points; -) The design and development of plant specific Safeguards equipment, including an on site laboratory for sample analysis; -) The development by the operator of an appropriate Nuclear Material accountancy system to facilitate their declaration obligations; -) The introduction of an inspection regime allowing comprehensive controls under the restrictions imposed by financial and Human Resources limitations; -) Optimization of the inspection effort by using unattended measuring stations, containment and surveillance systems and secure remote transmission of data to the regulator's headquarters. The paper is followed by the slides of the presentation. (authors)

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.

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

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)

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.

In-process hold-up as a measure of safeguards significance

International Nuclear Information System (INIS)

Hamlin, A.G.

1983-01-01

This paper examines the use of the in-process hold-up itself, as a measure of safeguards significance. It is argued that for any process plant it is possible to define design limits for in-process hold-up, outside which the plant will not operate, or will operate in a detectably abnormal manner. It follows, therefore, that if the in-process hold-up can be derived at frequent intervals by input/output analysis from the start of the campaign, the only diversion that can be made from it during that campaign is limited to the quantity necessary to move the apparent in-process hold-up from its normal operating condition to the upper limiting condition. It also follows that detection of this diversion is as positive for protracted diversion as for abrupt diversion. If that part of the in-process inventory that is only measurable by input/output analysis has an upper operating limit that differs from its normal operating limit by less than a significant safeguards quantity of the material in question, the IAEA's criteria for both quantity and timeliness can be met by a combination of input/output analysis to determine in-process hold-up during the campaign, together with a material balance over the campaign. The paper examines the possibility of applying this measure to process plants in general, discusses means of minimizing the in-process inventory that must be determined by input/output analysis, and the performance required of the input and output analysis. It concludes that with current precision of measurement and with one input and one output batch per day, each measured, the method would be satisfactory for a campaign lasting nearly a year and involving 6 tonnes of plutonium. The paper examines the considerable advantages in verification that would arise from limiting safeguards analyses to the two points of input and output. (author)

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.

Safeguards operations in the integral fast reactor fuel cycle

International Nuclear Information System (INIS)

Goff, K.M.; Benedict, R.W.; Brumbach, S.B.; Dickerman, C.E.; Tompot, R.W.

1994-01-01

Argonne National Laboratory is currently demonstrating the fuel cycle for the Integral Fast Reactor (IFR), an advanced reactor concept that takes advantage of the properties of metallic fuel and liquid metal cooling to offer significant improvements in reactor safety, operation, fuel-cycle economics, environmental protection, and safeguards. The IFR fuel cycle employs a pyrometallurgical process using molten salts and liquid metals to recover actinides from spent fuel. The safeguards aspects of the fuel cycle demonstration must be approved by the United States Department of Energy, but a further goal of the program is to develop a safeguards system that could gain acceptance from the Nuclear Regulatory Commission and International Atomic Energy Agency. This fuel cycle is described with emphasis on aspects that differ from aqueous reprocessing and on its improved safeguardability due to decreased attractiveness and diversion potential of all process streams, including the fuel product

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.

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

Advanced safeguards systems development for chemical processing plants. Final report for Fiscal Year 1979

International Nuclear Information System (INIS)

Johnson, C.E.

1980-01-01

A computer system is being installed by INEL to test and evaluate safeguards monitoring concepts in an operating nuclear fuel processing plant. Safeguards development sensors and instruments installed in the ICPP provide plant information to a computer data acquisition and analysis system. Objective of the system is to collect data from process and safeguards sensors and show how this data can be analyzed to detect diversion operations or improper plant operation, and to test the performance of the monitoring devices. Approximately one-third of the installation designs and one-eighth of the installations were completed in FY 1979. The ICPP processing schedule for FY 1980 permits installation of the remaining monitoring devices before process startup in the fourth quarter of FY 1980. All computer hardware was delivered and checked out in FY 1979. Computer software system designs were completed with the majority of the programming scheduled for FY 1980. Sensor and instrument development in FY 1979 emphasized device testing for ICPP monitoring applications

Advanced-safeguards systems development for chemical-processing plants. Final report for FY 1980

International Nuclear Information System (INIS)

Cartan, F.O.

1981-04-01

The program is installing a computer system to test and evaluate process monitoring as a new Safeguards function to supplement the usual physical security and accountability functions. Safeguards development sensors and instruments installed in the Idaho Chemical Processing Plant (ICPP) provide information via a data acquisition system to a Safeguards analysis computer. The monitoring function can significantly enhance current material control (accountability) and containment surveillance capabilities for domestic and international Safeguards uses. Installation of sensors and instruments in the ICPP was more than 75% complete in FY-1980. Installation work was halted at the request of ICPP operations near the end of the year to eliminate possible conflict with instrument calibrations prior to plant startup. Some improvements to the computer hardware were made during FY-1980. Sensor and instrument development during FY-1980 emphasized device testing for ICPP monitoring applications. Pressure transducers, pressure switches, a bubble flowmeter, and load cells were tested; an ultrasonic liquid-in-line sensor was developed and tested. Work on the portable, isotope-ratio mass spectrometer led to the comparison of the HP quadrupole instrument with a small magnetic instrument and to the selection of the quadrupole

Process monitoring in modern safeguards applications

International Nuclear Information System (INIS)

Ehinger, M.H.

1989-01-01

From the safeguards standpoint, regulatory requirements are finally moving into the modern world of communication and information processing. Gone are the days when the accountant with the green eye shade and arm bands made judgments on the material balance a month after the balance was closed. The most recent Nuclear Regulatory Commission (NRC) regulations and U.S. Department of Energy (DOE) orders have very strict standards for timeliness and sensitivity to loss or removal of material. The latest regulations recognize that plant operators have a lot of information on and control over the location and movement of material within their facilities. This information goes beyond that traditionally reported under accountability requirements. These new regulations allow facility operators to take credit for many of the more informal process controls

Integrated safeguards and security for a highly automated process

International Nuclear Information System (INIS)

Zack, N.R.; Hunteman, W.J.; Jaeger, C.D.

1993-01-01

Before the cancellation of the New Production Reactor Programs for the production of tritium, the reactors and associated processing were being designed to contain some of the most highly automated and remote systems conceived for a Department of Energy facility. Integrating safety, security, materials control and accountability (MC and A), and process systems at the proposed facilities would enhance the overall information and protection-in-depth available. Remote, automated fuel handling and assembly/disassembly techniques would deny access to the nuclear materials while upholding ALARA principles but would also require the full integration of all data/information systems. Such systems would greatly enhance MC and A as well as facilitate materials tracking. Physical protection systems would be connected with materials control features to cross check activities and help detect and resolve anomalies. This paper will discuss the results of a study of the safeguards and security benefits achieved from a highly automated and integrated remote nuclear facility and the impacts that such systems have on safeguards and computer and information security

Preliminary assessment of safeguardability on the concepture design of advanced spent fuel conditioning process

Energy Technology Data Exchange (ETDEWEB)

Lee, Sang Yoon; Ha, Jang Ho; Ko, Won Il; Song, Dae Yong; Kim, Ho Dong

2003-04-01

In this report, a preliminary study on the safeguardability of ACP (Advanced spent fuel Conditioning Process) was conducted with Los Alamos National Laboratory. The proposed ACP concept is an electrometallurgical treatment technique to convert oxide-type spent nuclear fuels into metal forms, which can achieve significant reduction of the volume and heat load of spent fuel to be stored and disposed of. For the safeguardability analysis of the ACP facility, sub-processes and their KMPs (Key Measurement Points) were defined first, and then their material flows were analyzed. Finally, the standard deviation of the Inventory Difference (ID) value of the facility was estimated with assumption by assuming international target values for the uncertainty of measurement methods and their uncertainty. From the preliminary calculation, we concluded that if the assumptions regarding measurement instruments can be achieved in a safeguards system for the ACP facility, the safeguards goals of International Atomic Energy Agency (IAEA) could be met. In the second phase of this study, further study on sensitivity analyses considering various factors such as measurement errors, facility capacities, MBA periods etc. may be needed.

Preliminary assessment of safeguardability on the concepture design of advanced spent fuel conditioning process

International Nuclear Information System (INIS)

Lee, Sang Yoon; Ha, Jang Ho; Ko, Won Il; Song, Dae Yong; Kim, Ho Dong

2003-04-01

In this report, a preliminary study on the safeguardability of ACP (Advanced spent fuel Conditioning Process) was conducted with Los Alamos National Laboratory. The proposed ACP concept is an electrometallurgical treatment technique to convert oxide-type spent nuclear fuels into metal forms, which can achieve significant reduction of the volume and heat load of spent fuel to be stored and disposed of. For the safeguardability analysis of the ACP facility, sub-processes and their KMPs (Key Measurement Points) were defined first, and then their material flows were analyzed. Finally, the standard deviation of the Inventory Difference (ID) value of the facility was estimated with assumption by assuming international target values for the uncertainty of measurement methods and their uncertainty. From the preliminary calculation, we concluded that if the assumptions regarding measurement instruments can be achieved in a safeguards system for the ACP facility, the safeguards goals of International Atomic Energy Agency (IAEA) could be met. In the second phase of this study, further study on sensitivity analyses considering various factors such as measurement errors, facility capacities, MBA periods etc. may be needed

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

Trial Application of the Facility Safeguardability Assessment Process to the NuScale SMR Design

Energy Technology Data Exchange (ETDEWEB)

Coles, Garill A.; Gitau, Ernest TN; Hockert, John; Zentner, Michael D.

2012-11-09

FSA is a screening process intended to focus a facility designer’s attention on the aspects of their facility or process design that would most benefit from application of SBD principles and practices. The process is meant to identify the most relevant guidance within the SBD tools for enhancing the safeguardability of the design. In fiscal year (FY) 2012, NNSA sponsored PNNL to evaluate the practical application of FSA by applying it to the NuScale small modular nuclear power plant. This report documents the application of the FSA process, presenting conclusions regarding its efficiency and robustness. It describes the NuScale safeguards design concept and presents functional "infrastructure" guidelines that were developed using the FSA process.

32 CFR Appendix D to Part 323 - Word Processing Center (WPC) Safeguards

Science.gov (United States)

2010-07-01

... DEFENSE (CONTINUED) PRIVACY PROGRAM DEFENSE LOGISTICS AGENCY PRIVACY PROGRAM Pt. 323, App. D Appendix D to... (WPCs) operating independent of the customer's function. However, managers of word processing systems... addressed. C. Safeguarding Information During Receipt. 1. The word processing manager will establish...

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

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

Development of data acquisition and processing software based on MS-Windows 3.X for safeguards

International Nuclear Information System (INIS)

Tan Yajun

1996-01-01

The development method of data acquisition and processing software based on MS-Windows 3.X for safeguards is presented. The paper describes the design methods of graphical user interface (GUI), multiwindow and multitask-based spectrum graph display, data acquisition and processing and the application of object-oriented programming (OOP). Using the package, an effective prototype design path can be found for MS-Windows-based software. The methods and programs have been applied in some safeguard non-destructive assay system

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

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)

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

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...

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)

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.

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

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

The nuclear safeguards system and the process of global governance accountability

Energy Technology Data Exchange (ETDEWEB)

Xavier, Roberto Salles, E-mail: xavier@cnen.gov.b [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Coordenacao Geral de Planejamento e Avaliacao

2011-07-01

Due to rising energy costs and climate concerns, nuclear energy is again being seriously considered as an energy source for several countries. Along with the resurgence of nuclear energy comes the concern of the world if these countries will develop their programs for the peaceful use of nuclear energy. If on one hand the growth potential of nuclear energy should not be stifled, on the other hand it is imperative that a climate of mutual trust is developed, respecting the right of each country to develop its nuclear program without taking a climate of mistrust to a possible 'intention' behind the pursuit of peaceful use of nuclear energy. Therefore, it is essential that appropriate mechanisms of accountability of global governance are institutionalized at the institutional architecture of the international process of nuclear safeguards, more specifically to the nuclear fuel cycle, so that abuses of power in this sphere does not happen, both by countries that aspire to develop projects nuclear, and by the suppliers of technology. In this context, the case study of Brazil and Argentina gained importance, because these two countries have a single binational organization of nuclear safeguards in the world: Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials - ABACC. In the theoretical question, the paper tries to understand what happens with the process of legitimacy and authority of the organizations of global governance by analyzing the degree of publicness and constrictiveness. This work intends to focus on the role of ABACC as an interstate institution of accountability, which has a key role to control the nation States of Brazil and Argentina regarding the appropriate use of nuclear material used in their programs, and analyze how this Agency behaves within of tension legitimacy-authority, taking into account existing studies on accountability in global governance. (author)

The nuclear safeguards system and the process of global governance accountability

International Nuclear Information System (INIS)

Xavier, Roberto Salles

2011-01-01

Due to rising energy costs and climate concerns, nuclear energy is again being seriously considered as an energy source for several countries. Along with the resurgence of nuclear energy comes the concern of the world if these countries will develop their programs for the peaceful use of nuclear energy. If on one hand the growth potential of nuclear energy should not be stifled, on the other hand it is imperative that a climate of mutual trust is developed, respecting the right of each country to develop its nuclear program without taking a climate of mistrust to a possible 'intention' behind the pursuit of peaceful use of nuclear energy. Therefore, it is essential that appropriate mechanisms of accountability of global governance are institutionalized at the institutional architecture of the international process of nuclear safeguards, more specifically to the nuclear fuel cycle, so that abuses of power in this sphere does not happen, both by countries that aspire to develop projects nuclear, and by the suppliers of technology. In this context, the case study of Brazil and Argentina gained importance, because these two countries have a single binational organization of nuclear safeguards in the world: Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials - ABACC. In the theoretical question, the paper tries to understand what happens with the process of legitimacy and authority of the organizations of global governance by analyzing the degree of publicness and constrictiveness. This work intends to focus on the role of ABACC as an interstate institution of accountability, which has a key role to control the nation States of Brazil and Argentina regarding the appropriate use of nuclear material used in their programs, and analyze how this Agency behaves within of tension legitimacy-authority, taking into account existing studies on accountability in global governance. (author)

Automatic image processing as a means of safeguarding nuclear material

International Nuclear Information System (INIS)

Kahnmeyer, W.; Willuhn, K.; Uebel, W.

1985-01-01

Problems involved in computerized analysis of pictures taken by automatic film or video cameras in the context of international safeguards implementation are described. They include technical ones as well as the need to establish objective criteria for assessing image information. In the near future automatic image processing systems will be useful in verifying the identity and integrity of IAEA seals. (author)

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)

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)

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).

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

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

Implementing Safeguards-by-Design

International Nuclear Information System (INIS)

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

2010-01-01

Excerpt Safeguards-by-Design (SBD) is an approach to the design and construction of nuclear facilities whereby safeguards are designed-in from the very beginning. It is a systematic and structured approach for fully integrating international and national safeguards (MC and A), physical security, and other proliferation barriers into the design and construction process for nuclear facilities. SBD is primarily a project management or project coordination challenge, and this report focuses on that aspect of SBD. The present report continues the work begun in 2008 and focuses specifically on the design process, or project management and coordination - the planning, definition, organization, coordination, scheduling and interaction of activities of the safeguards experts and stakeholders as they participate in the design and construction of a nuclear facility. It delineates the steps in a nuclear facility design and construction project, in order to provide the project context within which the safeguards design activities take place, describes the involvement of safeguards experts in the design process, the nature of their analyses, interactions and decisions, as well as describing the documents created and how they are used. Designing and constructing a nuclear facility is an extremely complex undertaking. The stakeholders in an actual project are many - owner, operator, State regulators, nuclear facility primary contractor, subcontractors (e.g. instrument suppliers), architect engineers, project management team, safeguards, safety and security experts, in addition to the IAEA and its team. The purpose of the present report is to provide a common basis for discussions amongst stakeholders to collaboratively develop a SBD approach that will be both practically useful and mutually beneficial. The principal conclusions from the present study are: (1) In the short term, the successful implementation of SBD is principally a project management problem. (2) Life-cycle cost

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

Since the INPRO Collaborative Project on Proliferation Resistance and Safeguardability Assessment Tools (PROSA) was launched in 2011, Member State experts have worked with the INPRO Section and the IAEA Department of Safeguards to develop a revised methodology for self-assessment of sustainability in the area of proliferation resistance of a nuclear energy system (NES). With the common understanding that there is ''no proliferation resistance without safeguards'' the revised approach emphasizes the evaluation of a new 'User Requirement' for ''safeguardability'', that combines metrics of effective and efficient implementation of IAEA Safeguards including ''Safeguards-by-Design'' principles. The assessment with safeguardability as the key issue has been devised as a linear process evaluating the NES against a ''Basic Principle'' in the area of proliferation resistance, answering fundamental questions related to safeguards: 1) Do a State's legal commitments, policies and practices provide credible assurance of the exclusively peaceful use of the NES, including a legal basis for verification activities by the IAEA? 2) Does design and operation of the NES facilitate the effective and efficient implementation of IAEA safeguards? To answer those questions, a questionnaire approach has been developed that clearly identifies gaps and weaknesses. Gaps include prospects for improvements and needs for research and development. In this context, the PROSA approach assesses the safeguardability of a NES using a layered ''Evaluation Questionnaire'' that defines Evaluation Parameters (EP), EP-related questions, Illustrative Tests and Screening Questions to present and structure the evidence of findings. An integral part of the assessment process is Safeguards-by-Design, the identification of potential diversion, misuse and concealment strategies (coarse diversion path

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.

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

Safeguarding a future industrial reprocessing plant

International Nuclear Information System (INIS)

1978-11-01

This paper is submitted to Working Group 5, Sub-Group B for information. It is being submitted to Working Group 4 for discussion at their meeting in January 1979 and shows that by a combination of accountancy, surveillance and containment a reliable safeguards system can be designed for the reprocessing of fuels of the BWR and PWR type. Its arguments can, in general terms, be applied to plants for reprocessing LMFBR fuels, with due allowance for future advances which should improve our overall knowledge of the reliability of safeguards systems. In the reprocessing of fast reactor (LMFBR) fuels, as compared with LWR fuels, the main differences are the higher plutonium concentration and lower heavy metal throughput in the early stages of the reprocessing operations. At later stages in the process (after plutonium/uranium separation) the plants could be similar and have similar safeguarding problems. Plants for reprocessing LMFBR on a commercial scale will not be in operation for a number of years. In these plants greater attention may have to be paid to safeguards at the early stages, especially to waste/raffinate streams, than in the PWR/BWR reprocessing plant. The actual balance between containment, surveillance and accountancy adopted will depend on the status of the technology of safeguards and reprocessing. It can be anticipated that improvements to measurement systems will be made which may allow greater reliance on actual measurement. Treatment and recycle of solid wastes will advance and could therefore lead to improvements in accountancy in, for example, the ''head-end''

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.

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)

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

Multi-Level Policy Dialogues, Processes, and Actions: Challenges and Opportunities for National REDD+ Safeguards Measurement, Reporting, and Verification (MRV

Directory of Open Access Journals (Sweden)

Pamela Jagger

2014-09-01

Full Text Available REDD+ social safeguards have gained increasing attention in numerous forums. This paper reviews the evolution of multi-level policy dialogues, processes, and actions related to REDD+ social safeguards (e.g., Cancun Safeguards 1–5 among policy makers, civil society organizations, and within the media in Brazil, Indonesia and Tanzania, three countries with well advanced REDD+ programs. We find that progress on core aspects of social safeguards is uneven across the three countries. Brazil is by far the most advanced having drafted a REDD+ social safeguards policy. Both Brazil and Indonesia have benefited from progress made by strong sub-national entities in the operationalization of REDD+ safeguards including free prior and informed consent (FPIC, participation, and benefit sharing. Tanzania has weakly articulated how social safeguards will be operationalized and has a more top-down approach. We conclude that in all three countries, measuring, reporting and verifying progress on social safeguards is likely to be a complex issue. Stakeholders with vested interests in REDD+ social safeguards operate in polycentric rather than nested systems, suggesting that aggregation of information from local to national-scale will be a challenge. However, polycentric systems are also likely to support more transparent and comprehensive safeguards systems. Clear direction from the international community and financing for REDD+ safeguard MRV is essential if REDD+ social safeguards are to be meaningfully integrated into forest-based climate mitigation strategies.

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

The application of a Safeguards-by-Design (SBD) process for new nuclear facilities can reduce proliferation risks. A multi-laboratory team was sponsored in Fiscal Year (FY) 2008 to define a SBD process and determine how it could be incorporated into existing facility design and construction processes. The possibility to significantly influence major design features, such as process selection and plant layout, largely ends with the conceptual design step. Therefore SBD's principal focus must be on the early inclusion of safeguards requirements and the early identification of beneficial design features. The result could help form the basis for a new international norm for integrating safeguards into facility design. This is an interim report describing progress and project status as of the end of FY08. In this effort, SBD is defined as a structured approach to ensure the timely, efficient, and cost-effective integration of international and national safeguards, physical security, and other nonproliferation objectives into the overall design process for a nuclear facility. A key objective is to ensure that security and nonproliferation issues are considered when weighing facility design alternatives. Central to the work completed in FY08 was a study in which a SBD process was developed in the context of the current DOE facility acquisition process. The DOE study enabled the development of a 'SBD design loop' that is suitable for use in any facility design process. It is a graded, iterative process that incorporates safeguards concerns throughout the conceptual, preliminary and final design processes. Additionally, a set of proposed design principles for SBD was developed. A 'Generic SBD Process' was then developed. Key features of the process include the initiation of safeguards design activities in the pre-conceptual planning phase, early incorporation of safeguards requirements into the project requirements, early appointment of an SBD team, and participation in

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

The application of a Safeguards-by-Design (SBD) process for new nuclear facilities can reduce proliferation risks. A multi-laboratory team was sponsored in Fiscal Year (FY) 2008 to define a SBD process and determine how it could be incorporated into existing facility design and construction processes. The possibility to significantly influence major design features, such as process selection and plant layout, largely ends with the conceptual design step. Therefore SBD’s principal focus must be on the early inclusion of safeguards requirements and the early identification of beneficial design features. The result could help form the basis for a new international norm for integrating safeguards into facility design. This is an interim report describing progress and project status as of the end of FY08. In this effort, SBD is defined as a structured approach to ensure the timely, efficient, and cost-effective integration of international and national safeguards, physical security, and other nonproliferation objectives into the overall design process for a nuclear facility. A key objective is to ensure that security and nonproliferation issues are considered when weighing facility design alternatives. Central to the work completed in FY08 was a study in which a SBD process was developed in the context of the current DOE facility acquisition process. The DOE study enabled the development of a “SBD design loop” that is suitable for use in any facility design process. It is a graded, iterative process that incorporates safeguards concerns throughout the conceptual, preliminary and final design processes. Additionally, a set of proposed design principles for SBD was developed. A “Generic SBD Process” was then developed. Key features of the process include the initiation of safeguards design activities in the pre-conceptual planning phase, early incorporation of safeguards requirements into the project requirements, early appointment of an SBD team, and

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

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

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

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

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

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

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

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.

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

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).

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).

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

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

Safeguards by Design - Experiences from New Nuclear Installation

International Nuclear Information System (INIS)

Okko, O.; Honkamaa, T.; Kuusi, A.; Rautjaervi, J.

2010-01-01

The experiences obtained from the current construction projects at Olkiluoto clearly point out the need to introduce the safeguards requirements into facility design process at an early stage. The early Design Information is completed, in principle, before the construction. However, during the design of containment, surveillance systems, and non-destructive assay equipment and their cabling, the design requirements for safeguards systems were not available either for the new reactor unit or for the disposal plant with a geological repository. Typically, the official Design Information documents are not available early enough for efficient integration of safeguards systems into new facilities. In case of the Olkiluoto projects, this was due to understandable reasons: at the new reactor unit the design acceptance by the ordering company and by the nuclear safety authorities was a long process, ongoing simultaneously with parts of the construction; and at the geological repository the national legislation assigns the repository the status of a nuclear facility only after the initial construction and research phase of the repository when the long-term safety of the disposal concept is demonstrated. As similar factors are likely to delay the completion of the official Design Information documents with any new reactor projects until the construction is well underway and efficient integration of safeguards systems is impossible. Therefore, the proliferation resistance of new nuclear installations should be addressed in the design phase before the official Design Information documents are finished. This approach was demonstrated with the enlargement of the Olkiluoto spent fuel storage building. For this approach to work, strong national contribution is needed to facilitate the early communication and exchange of information between the IAEA and the other stakeholders to enable the design of facilities that can be efficiently safeguarded. With the renaissance of nuclear

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

Holdup-related issues in safeguarding of nuclear materials

International Nuclear Information System (INIS)

Pillay, K.K.S.

1988-03-01

Residual inventories of special nuclear materials (SNM) remaining in processing facilities (holdup) are recognized as an insidious problem for both safety and safeguards. This paper identifies some of the issues that are of concern to the safeguards community at-large that are related to holdup of SNM in large-scale process equipment. These issues range from basic technologies of SNM production to changing regulatory requirements to meet the needs of safeguarding nuclear materials. Although there are no magic formulas to resolve these issues, there are several initiatives that could be taken in areas of facility design, plant operation, personnel training, SNM monitoring, and regulatory guidelines to minimize the problems of holdup and thereby improve both safety and safeguards at nuclear material processing plants. 8 refs

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

Energy Technology Data Exchange (ETDEWEB)

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

2009-09-01

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

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.

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.

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

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)

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)

To Russia with love: how the Australian Government's much vaunted safeguards policy has been watered down, step by step

International Nuclear Information System (INIS)

Milliken, R.

1981-01-01

Australia's uranium safeguards policy was announced in May 1977. The following conditions were included: no contracts could be signed until safeguards agreements had been concluded; uranium sold must remain Australian owned until it had been processed into a form attracting IAEA safeguards inspection; and prior Australian consent was required before a customer could reprocess Australian uranium, transfer it to a third country, or enrich it to a grade higher than that needed for normal power plants. Australia has signed 9 safeguards agreements and two more are due to be finalised soon. The author discusses changes in policy since the first agreement was signed. One problem has been conflict between commercial and safeguards issues

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)

A safeguards case study of the Nuclear Materials and equipment corporation uranium processing plant Apollo, Pennsylvania. Appendix B with proprietary information removed. Staff technical report

International Nuclear Information System (INIS)

Altman, W.; Hockert, J.; Quinn, E.

1980-04-01

The report characterizes the Atomic Energy Commission safeguards requirements and the safeguards systems and procedures in place at the Nuclear Materials and Equipment (NUMEC) uranium processing plant in Apollo, Pennsylvania during the spring of 1964. Based upon this characterization, a list of safeguards weaknesses which would be considered deficiencies under 1979 requirements is developed. Appendixes A and B to the report provide a detailed characterization of AEC safeguards requirements as well as a side by side comparison of NUMEC's safeguards program in 1964 with the safeguards program currently required of a comparable licensed facility

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.)

Integrating Safeguards and Security with Safety into Design

International Nuclear Information System (INIS)

Bean, Robert S.; Hockert, John W.; Hebditch, David J.

2009-01-01

There is a need to minimize security risks, proliferation hazards, and safety risks in the design of new nuclear facilities in a global environment of nuclear power expansion, while improving the synergy of major design features and raising operational efficiency. In 2008, the U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA) launched the Next Generation Safeguards Initiative (NGSI) covering many safeguards areas. One of these, launched by NNSA with support of the DOE Office of Nuclear Energy, was a multi-laboratory project, led by the Idaho National Laboratory (INL), to develop safeguards by design. The proposed Safeguards-by-Design (SBD) process has been developed as a structured approach to ensure the timely, efficient, and cost effective integration of international safeguards and other nonproliferation barriers with national material control and accountability, physical security, and safety objectives into the overall design process for the nuclear facility lifecycle. A graded, iterative process was developed to integrate these areas throughout the project phases. It identified activities, deliverables, interfaces, and hold points covering both domestic regulatory requirements and international safeguards using the DOE regulatory environment as exemplar to provide a framework and guidance for project management and integration of safety with security during design. Further work, reported in this paper, created a generalized SBD process which could also be employed within the licensed nuclear industry and internationally for design of new facilities. Several tools for integrating safeguards, safety, and security into design are discussed here. SBD appears complementary to the EFCOG TROSSI process for security and safety integration created in 2006, which focuses on standardized upgrades to enable existing DOE facilities to meet a more severe design basis threat. A collaborative approach is suggested.

Computer-based safeguards information and accounting system

International Nuclear Information System (INIS)

1977-01-01

Acquiring, processing and analysing information about inventories and flow of nuclear materials are essential parts of IAEA safeguards. Safeguards information originates from several sources. The information to be provided is specified in the various safeguards agreements between the States and the IAEA, including both NPT agreements and safeguards trilateral agreements. Most of the safeguards information currently received by the IAEA is contained in accounting reports from the States party to the NPT. Within the frame of the material balance concept of NPT, three types of reports are provided to the IAEA by the States: Physical Inventory Listings (PIL); Inventory Change Reports (ICR); Material Balance Reports (MBR). In addition, facility design information is reported when NPT safeguards are applied and whenever there is a change in the facility or its operation. Based on this data, an accounting system is used to make available such information as the book inventories of nuclear material as a function of time, material balance evaluations, and analysis of shipments versus receipts of nuclear material. A second source of NPT safeguards information is the inspection activities carried out in the field as a necessary counterpart for verification of the data presented by the States in their accounting reports. The processing of inspection reports and other inspection data is carried out by the present system in a provisional manner until a new system, which is under development is available. The major effort currently is directed not to computer processing but toward developing and applying uniform inspection procedures and information requirements. A third source of NPT safeguards information is advanced notifications and notifications of transfer of source materials before the starting point of safeguards. Since, however, the States are not completely aware of the need and requirement to provide these data, this is a point to be emphasized in future workshops and

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.

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)

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

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

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)

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.)

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

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.

Development of a Safeguards Approach for a Pyroprocessing Plant by IAEA Member State Support Program

International Nuclear Information System (INIS)

Shin, H. S.; Kim, H. D.; Song, D. Y.; Eom, S. H.; Lee, T. H.; Ahn, S. K.; Park, S. H.; Han, B. Y.; Choi, Y.

2012-01-01

The objective of this project is to analyze the safeguard ability of pyroprocess facility and to establish the safeguards system for pyroprocess by developing the technology of nuclear material accounting for unit process, surveillance technology and nuclear characteristic analysis technology which are needed to demonstrate the safeguards technology of pyroprocess. Therefore, the development of a safeguards approach for pyroprocessing facilities is required as the interest of pyroprocessing increases. Regarding this issue, the IAEA made a contract the 3-years long Member State Support Program (MSSP) for the 'Support for Development of a Safeguards Approach for a Pyroprocessing Plant' with the Republic of Korea (ROK) in July 2008. Even though the pyroprocess technology is currently being developed all over the world, its safeguards approach has not been established yet, and especially, nuclear material accountancy technology which is the core of safeguards has not been established as well. Therefore, the development of new accountancy technology which is appropriate for the construction of pyroprocess facility is needed. Due to the nature of the process, pyroprocess has various kinds of process material form, and the composition of Pu and U isotopes included in process material is not homogeneous. Also, the existing nuclear material accountancy technology for a wet reprocessing facility is hard to apply because of a large quantity of gamma-ray radiation which is emitted from the fissile products in process material. In this report, the study for the development of a safeguards approach for a pyroprocessing plant pyroprocessing has been described. As the previous results six pyroprocessing facility concepts suggested by US, Japan, and Republic of Korea had been summarized and analyzed, and the determination principles were established to determine a reference pyroprocessing facility concept. The reference pyroprocessing facility was determined to be the ESPF of KAERI

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)

An analysis of a regional nuclear safeguards organisation: the European Atomic Energy Community (EURATOM) and the development of nuclear safeguards in Western Europe

International Nuclear Information System (INIS)

Howlett, Darryl.

1988-08-01

This thesis argues that the nuclear safeguards system implemented by EURATOM in Western Europe has come to fruition as a result of a complex political process. This process has involved negotiations over the exact limits on safeguards interventions into the nuclear affairs of the European Community. There are two dimensions to these negotiations. On the one hand, they involve EURATOM and its member states over the necessary limits on safeguards intervention in member states' domestic nuclear affairs. On the other, there are negotiations between EURATOM and several actors outside the region, particularly the International Atomic Energy Agency. The thesis concludes by arguing that international safeguards organisations, of which EURATOM is a regional example, have made important contributions to arms control and international security. In the process, certain kinds of precedents and procedures which have potential for broader application have been established. (author)

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

Timely integration of safeguards and security with projects at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Price, R.; Blount, P.M.; Garcia, S.W.; Gonzales, R.L.; Salazar, J.B.; Campbell, C.H.

2004-01-01

The Safeguards and Security (S and S) Requirements Integration Team at Los Alamos National Laboratory (LANL) has developed and implemented an innovative management process that will be described in detail. This process systematically integrates S and S planning into construction, facility modifications or upgrades, mission changes, and operational projects. It extends and expands the opportunities provided by the DOE project management manual, DOE M 413.3-1. Through a series of LANL documents, a process is defined and implemented that formally identifies an S and S professional to oversee, coordinate, facilitate, and communicate among the identified S and S organizations and the project organizations over the life cycle of the project. The derived benefits, namely (1) elimination/reduction of re-work or costly retrofitting, (2) overall project cost savings because of timely and improved planning, (3) formal documentation, and (4) support of Integrated Safeguards and Security Management at LANL, will be discussed. How many times, during the construction of a new facility or the modification of an existing facility, have the persons responsible for the project waited until the last possible minute or until after construction is completed to approach the security organizations for their help in safeguarding and securing the facility? It's almost like, 'Oh, by the way, do we need access control and a fence around this building and just what are we going to do with our classified anyway?' Not only is it usually difficult; it's also typically expensive to retrofit or plan for safeguards and security after the fact. Safeguards and security organizations are often blamed for budget overruns and delays in facility occupancy and program startup, but these problems are usually due to poor front-end planning. In an effort to help projects engage safeguards and security in the pre-conceptual or conceptual stages, we implemented a high level formality of operations. We

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

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

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.

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

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

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

Safeguards for the atom

Energy Technology Data Exchange (ETDEWEB)

NONE

1959-10-15

the Agency to set up a system of safeguards that would guarantee that no nuclear material at all could be diverted to unauthorized use. What the Agency intends is to apply its safeguards in such a manner as to achieve a high probability of detecting the diversion of even small quantities of materials, and when larger quantities are involved, to make detection almost certain. The need for safeguards would obviously arise in the case of fissile materials, because of their possible use in the production of weapons. The Agency safeguards may, therefore, be applied - depending on the quantity and other factors involved - to all types of these materials, namely natural uranium, thorium, enriched uranium, uranium 235, uranium 233 and plutonium. The greater the quantity of the actual fissile substances involved and the greater the possibility of diversion, the greater will be the need for safeguards. Details of the safeguards procedures are yet to be finally approved. Broadly speaking, they are expected to provide, inter alia, for the approval by the Agency of designs of facilities or installations in which materials subject to Agency safeguards are to be used, processed, recovered, produced or stored; the maintenance by the State concerned of records concerning accountability, inventory, operation and waste disposal; submission of periodic reports to the Agency; the deposit of excess fissile materials with the Agency; and visits by Agency representatives to the locations where the materials or facilities provided by the Agency are in use. Procedures for the application of health and safety measures will be set out in similar detail. The Agency has already provided for the application of Agency safeguards to the project under which Japan has bought from it three tons of natural uranium for use in a research reactor. A number of bilateral agreements also contain clauses referring to the possible application of Agency safeguards to projects to be carried out under the

Safeguards for the atom

International Nuclear Information System (INIS)

1959-01-01

the Agency to set up a system of safeguards that would guarantee that no nuclear material at all could be diverted to unauthorized use. What the Agency intends is to apply its safeguards in such a manner as to achieve a high probability of detecting the diversion of even small quantities of materials, and when larger quantities are involved, to make detection almost certain. The need for safeguards would obviously arise in the case of fissile materials, because of their possible use in the production of weapons. The Agency safeguards may, therefore, be applied - depending on the quantity and other factors involved - to all types of these materials, namely natural uranium, thorium, enriched uranium, uranium 235, uranium 233 and plutonium. The greater the quantity of the actual fissile substances involved and the greater the possibility of diversion, the greater will be the need for safeguards. Details of the safeguards procedures are yet to be finally approved. Broadly speaking, they are expected to provide, inter alia, for the approval by the Agency of designs of facilities or installations in which materials subject to Agency safeguards are to be used, processed, recovered, produced or stored; the maintenance by the State concerned of records concerning accountability, inventory, operation and waste disposal; submission of periodic reports to the Agency; the deposit of excess fissile materials with the Agency; and visits by Agency representatives to the locations where the materials or facilities provided by the Agency are in use. Procedures for the application of health and safety measures will be set out in similar detail. The Agency has already provided for the application of Agency safeguards to the project under which Japan has bought from it three tons of natural uranium for use in a research reactor. A number of bilateral agreements also contain clauses referring to the possible application of Agency safeguards to projects to be carried out under the

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

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

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

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)

Technical Solution for Improved Safeguards/State Cooperation

International Nuclear Information System (INIS)

Miller, S.

2015-01-01

This paper will discuss an information technology solution to allow the IAEA Safeguards Department to improve cooperation with States. The solution will be a portal or hub to integrate the information, processes, and people between Safeguards and States. It will allow for two-way communication and collaboration between Safeguards staff and State representatives. This paper discusses the information security challenges inherent in building such a system. It proposes technical architectures that might allow the existing integration approach (e.g., encrypted email exchange) to be kept, while expanding it to include modern integration technologies (e.g., web services), as well explorer new collaborative web technologies. It looks at current Safeguards processes and approaches to cooperation and discusses efficiencies that could be achieved through the adoption of this technology solution. Example process areas for improvement include: a) Safeguards Agreements: States are obligated to submit data on their nuclear programme to the IAEA on a periodic basis. Declarations are received through two separate systems using encrypted email. The proposed solution would allow for enhanced exchange of declaration where States can submit any type of declaration using one system. When declarations are received and validated, an acknowledgement would automatically be sent to the State. The solution would provide the Safeguards Department the ability to ask for clarification as well as collaborate on the submitted declarations. Both the question and the response would be recorded in the system. The solution could also integrate tools allowing declarations to be added directly and validated before submission. b) Other areas that could benefit from this solution include declarations from States with small quantities protocol, facility declarations, as well as systems that support extra-budgetary funding (e.g., SPRICS). (author)

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.

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

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

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.

Safeguardability of a commercial-scaled ACP facility

Energy Technology Data Exchange (ETDEWEB)

Ko, Won Il; Lee, S. Y.; Kim, H. D.; Ha, J. H.; Song, D. Y.; Lee, T. H

2004-07-01

The Advanced spent fuel Conditioning Process (ACP) is an electro-metallurgical treatment technique to convert oxide-type spent nuclear fuel into a metallic form. This report documents a preliminary study on the safeguardability of ACP. The sub-processes and material flow of the pilot scale ACP facility were designed for this study. Then, their Material Balance Areas (MBA) and Key Measurement Point (KMP) were defined based on diversion scenario analysis. Finally, the limit of error in the MUF value was estimated using international target values for the uncertainty of measurement methods. Based on the results of preliminary study, we concluded that the safeguards goals of International Atomic Energy Agency (IAEA) could be met if the assumptions regarding measurement instruments can be achieved in a safeguards system for the ACP facility.

Safeguardability of a commercial-scaled ACP facility

International Nuclear Information System (INIS)

Ko, Won Il; Lee, S. Y.; Kim, H. D.; Ha, J. H.; Song, D. Y.; Lee, T. H.

2004-07-01

The Advanced spent fuel Conditioning Process (ACP) is an electro-metallurgical treatment technique to convert oxide-type spent nuclear fuel into a metallic form. This report documents a preliminary study on the safeguardability of ACP. The sub-processes and material flow of the pilot scale ACP facility were designed for this study. Then, their Material Balance Areas (MBA) and Key Measurement Point (KMP) were defined based on diversion scenario analysis. Finally, the limit of error in the MUF value was estimated using international target values for the uncertainty of measurement methods. Based on the results of preliminary study, we concluded that the safeguards goals of International Atomic Energy Agency (IAEA) could be met if the assumptions regarding measurement instruments can be achieved in a safeguards system for the ACP facility

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.

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.

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

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)

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

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)

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

Safeguards uses of confirmatory measurements

International Nuclear Information System (INIS)

Coulter, C.A.

1985-01-01

An analysis is made of the role of shipper and receiver measurements in safeguarding special nuclear materials (SNM) transferred from one facility to another, with emphasis on the case where the receiver requires an analytical accounting measurement of the transferred SNM and does not need the material for process purposes at the time of receipt. Seven possible diversion periods are considered, ranging from the interval between the shipper's final accounting measurement on the material and the time it is placed in the shipper's vault, through the actual transport of the material between facilities, to the time the material is removed from the receiver's vault and placed in the process. The detection power of various combinations of six possible shipper/receiver measurements for these diversion opportunities is then evaluated; the measurements considered include the shipper's and receiver's accounting measurements, the latter at two possible times, and various nondestructive assay (NDA) confirmatory measurements. It is concluded that all safeguards measurement objectives can be met by a combination of a shipper's accounting measurement at the time the material is removed from the process, an appropriate shipper's NDA confirmatory measurement either immediately after canning or immediately before shipping, an equivalent receiver's NDA confirmatory measurement immediately after the material is received, and a receiver's accounting measurement when the material is placed in the process. Furthermore, it is found that a receiver's analytical accounting measurement immediately after receipt when the material is not yet required for process has dubious safeguards value

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)

An American Academy for Training Safeguards Inspectors - An Idea Revisited

International Nuclear Information System (INIS)

Durst, Philip Casey; Bean, Robert

2010-01-01

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

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)

Due Diligence Processes for Public Acquisition of Mining-Impacted Landscapes

Science.gov (United States)

Martin, E.; Monohan, C.; Keeble-Toll, A. K.

2016-12-01

The acquisition of public land is critical for achieving conservation and habitat goals in rural regions projected to experience continuously high rates of population growth. To ensure that public funds are utilized responsibly in the purchase of conservation easements appropriate due diligence processes must be established that limit landowner liability post-acquisition. Traditional methods of characterizing contamination in regions where legacy mining activities were prevalent may not utilize current scientific knowledge and understanding of contaminant fate, transport and bioavailability, and therefore are likely to have type two error. Agency prescribed assessment methods utilized under CERLA in many cases fail to detect contamination that presents liability issues by failing to require water quality sampling that would reveal offsite transport potential of contaminants posing human health risks, including mercury. Historical analysis can be used to inform judgmental sampling to identify hotspots and contaminants of concern. Land acquisition projects at two historic mine sites in Nevada County, California, the Champion Mine Complex and the Black Swan Preserve have established the necessity of re-thinking due diligence processes for mining-impacted landscapes. These pilot projects demonstrate that pre-acquisition assessment in the Gold Country must include judgmental sampling and evaluation of contaminant transport. Best practices using the current scientific knowledge must be codified by agencies, consultants, and NGOs in order to ensure responsible use of public funds and to safeguard public health.

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.

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

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)

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

Design of integrated safeguards systems for nuclear facilities

International Nuclear Information System (INIS)

de Montmollin, J.M.; Walton, R.B.

1976-01-01

Safeguards systems that are capable of countering postulated threats to nuclear facilities must be closely integrated with plant layout and processes if they are to be effective and if potentially severe impacts on plant operations are to be averted. A facilities safeguards system suitable for a production plant is described in which the traditional elements of physical protection and periodic material-balance accounting are extended and augmented to provide close control of material flows. Discrete material items are subjected to direct, overriding physical control where appropriate. Materials in closely coupled process streams are protected by on-line NDA and weight measurements, with rapid computation of material balances to provide immediate indication of large-scale diversion. The system provides an information and actions at the safeguards/operations interface

Design of integrated safeguards systems for nuclear facilities

International Nuclear Information System (INIS)

de Montmollin, J.M.; Walton, R.B.

1978-06-01

Safeguards systems that are capable of countering postulated threats to nuclear facilities must be closely integrated with plant layout and processes if they are to be effective and if potentially-severe impacts on plant operations are to be averted. This paper describes a facilities safeguards system suitable for production plant, in which the traditional elements of physical protection and periodic material-balance accounting are extended and augmented to provide close control of material flows. Discrete material items are subjected to direct, overriding physical control where appropriate. Materials in closely-coupled process streams are protected by on-line NDA and weight measurements, with rapid computation of material balances to provide immediate indication of large-scale diversion. The system provides information and actions at the safeguards/operations interface

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.

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.

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.

Design considerations for an integrated safeguards system for fuel-reprocessng plants

International Nuclear Information System (INIS)

Cartan, F.O.

1982-05-01

This report presents design ideas for safeguards systems in nuclear fuels reprocessing plants. The report summarizes general safeguards requirements and describes a safeguards system concept being developed and tested at the Idaho Chemical Processing Plant. The report gives some general concepts intended for design consideration and a checklist of specific problems that should be considered. The report is intended as an aid for the safeguards system designer and as a source of useful information

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

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

Safeguards approaches for conversion and gas centrifuge enrichment plants

International Nuclear Information System (INIS)

Stanuch, C.; Whitaker, M.; Lockwood, D.; Boyer, B.

2013-01-01

This paper describes recent studies and investigations of new safeguards measures and inspection tools to strengthen international safeguards at GCEPs (Gas Centrifuge Enrichment Plants) and conversion plants. The IAEA has indicated that continuous, unattended process monitoring should play a central role in future safeguards approaches for conversion plants and GCEPs. Monitoring safeguards relevant information from accountancy scales, process load cells, and unit header pipes can make existing safeguards approaches more efficient by replacing repetitive, routine, labor-intensive inspection activities with automated systems. These systems can make the safeguards approach more effective by addressing more completely the safeguards objectives at these facilities. Automated collection and analysis of the data can further enable the IAEA to move towards a fully-information driven inspection regime with randomized (from the operator's perspective), short-notice inspections. The reduction in repetitive on-site inspection activities would also be beneficial to plant operators, but only if sensitive and proprietary information can be protected and the new systems prove to be reliable. New facilities that incorporate Safeguards by Design into the earliest design stages can facilitate the effective DIV (Design Information Verification) of the plant to allow the inspectors to analyze the capacity of the plant, to project maximum production from the plant, and to provide a focus on the areas in the plant where credible diversion scenarios could be attempted. Facilitating efficient nuclear material accountancy by simplifying process pipework and making flow measurement points more accessible can allow for easier estimation of plant holdup and a potential reduction in the number of person-days of inspection. Lastly, a universal monitoring standard that tracks the location, movement, and use of UF 6 cylinders may enhance the efficiency of operations at industry sites and would

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

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

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

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

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

Advanced Safeguards Technology Road-map for the Global Nuclear Energy Partnership

International Nuclear Information System (INIS)

Miller, M.C.; Tobin, S.; Smith, L.E.; Ehinger, M.; Dougan, A.; Cipiti, B.; Bakel, A.; Bean, R.

2008-01-01

Strengthening the nonproliferation regime, including advanced safeguards, is a cornerstone of the Global Nuclear Energy Partnership (GNEP). To meet these challenges, the Safeguards Campaign was formed, whose mission is to provide research and technology development for the foundation of next generation safeguards systems for implementation in U.S. GNEP facilities. The Safeguards Campaign works closely with the Nuclear Nonproliferation and International Security department (NA-24) of NNSA (National Nuclear Safety Administration) to ensure that technology developed for domestic safeguards applications are optimum with respect to international safeguards use. A major milestone of the program this year has been the development of the advanced safeguards technology road-map. This paper will broadly describe the road-map, which provides a path to next generation safeguards systems including advanced instrumentation; process monitoring; data integration, protection, and analysis; and system level evaluation and knowledge extraction for real time applications. (authors)

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)

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

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.

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

Office of Safeguards and Security - Operational Interface

International Nuclear Information System (INIS)

Hammond, G.A.

1987-01-01

The mission of the Office of Safeguards and Security (OSS), Department of Energy (DOE) is to: Develop policy and programs to protect DOE facilities, nuclear materials, and classified information; Provide oversight for safeguards and security operations; Direct research and development (RandD) to support the protection program; and Strengthen international safeguards in support of nonproliferation policy. Objectives are to maintain an integrated safeguards and security system that is effective against a wide range of threats, and do so in a manner to minimize impacts on facility operation. Implementation is the responsibility of field offices and contractors operating DOE facilities. The OSS-operational interface is the focus of this discussion with emphasis on RandD to meet user needs. The scope and project selection process will be discussed along with information required for evaluation, and field operational planning and budgeting commitments to permit implementation of successful RandD results

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.

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)

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.

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

Safeguarding aspects of large-scale commercial reprocessing plants

International Nuclear Information System (INIS)

1979-03-01

The paper points out that several solutions to the problems of safeguarding large-scale plants have been put forward: (1) Increased measurement accuracy. This does not remove the problem of timely detection. (2) Continuous in-process measurement. As yet unproven and likely to be costly. (3) More extensive use of containment and surveillance. The latter appears to be feasible but requires the incorporation of safeguards into plant design and sufficient redundancy to protect the operators interests. The advantages of altering the emphasis of safeguards philosophy from quantitative goals to the analysis of diversion strategies should be considered

Development of DUPIC safeguards technology

International Nuclear Information System (INIS)

Kim, H. D.; Kang, H. Y.; Ko, W. I.

2002-05-01

DUPIC safeguards R and D in the second phase has focused on the development of nuclear material measurement system and its operation and verification, the development of nuclear material control and accounting system, and the development of remote and unmanned containment/surveillance system. Of them, the nuclear material measurement system was authenticated from IAEA and officially used for IAEA and domestic safeguards activities in DFDF. It was also verified that the system could be used for quality control of DUPIC process. It is recognised that the diagnostic software using neural network and remote and unmanned containment/surveillance system developed here could be key technologies to go into remote and near-real time monitoring system. The result of this project will eventually contribute to similar nuclear fuel cycles like MOX and pyroprocessing facility as well as the effective implementation of DUPIC safeguards. In addition, it will be helpful to enhance international confidence build-up in the peaceful use of spent fuel material

Improved IAEA safeguards for closed nuclear fuel cycles

International Nuclear Information System (INIS)

1978-12-01

The paper recognises the limitations of nuclear material accountancy in applying safeguards to future large scale processing plants. For those plants the following will be necessary: (i) The inclusion of safeguards requirements in design criteria. (ii) Extensive application of containment and surveillance with monitors on personnel and goods exits, pipework, tanks, etc. (iii) Continuous inspectorate measurement of input and output flows. Local IAEA laboratories to ensure timeliness. (iv) Upgrading of process control information to enable the inspectorate to monitor the in-process inventory. The inspectorates knowledge of the in-process inventory will be valuable in their assessment of any alarms given by the containment-surveillance system

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)

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

Institutionalizing Safeguards By Design for Nuclear Facilities

International Nuclear Information System (INIS)

Morgan, James B.; Kovacic, Donald N.; Whitaker, J. Michael

2008-01-01

Safeguards for nuclear facilities can be significantly improved by developing and implementing methodologies for integrating proliferation resistance into the design of new facilities. This paper proposes a method to systematically analyze a facility's processes, systems, equipment, structures and management controls to ensure that all relevant proliferation scenarios that could potentially result in unacceptable consequences have been identified, evaluated and mitigated. This approach could be institutionalized into a country's regulatory structure similar to the way facilities are licensed to operate safely and are monitored through inspections and incident reporting to ensure compliance with domestic and international safeguards. Furthermore, taking credit for existing systems and equipment that have been analyzed and approved to assure a facility's reliable and safe operations will reduce the overall cost of implementing intrinsic and extrinsic proliferation-resistant features. The ultimate goal is to integrate safety, reliability, security and safeguards operations into the design of new facilities to effectively and efficiently prevent diversion, theft and misuse of nuclear material and sensitive technologies at both the facility and state level. To facilitate this approach at the facility level, this paper discusses an integrated proliferation resistance analysis (IPRA) process. If effectively implemented, this integrated approach will also facilitate the application of International Atomic Energy Agency (IAEA) safeguards

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

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

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

Developing the information management system for safeguards national inspection

International Nuclear Information System (INIS)

Park, S. J.; Jeon, I.; Park, W. S.; Min, K. S.

2003-01-01

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

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

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

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

HARMONISASI REGULASI DAN EFEKTIVITAS KELEMBAGAAN SAFEGUARD DI INDONESIA

Directory of Open Access Journals (Sweden)

Abdurrahman Alfaqiih

2012-06-01

Full Text Available The implementation of WTO agreement is not easy in accordance with the estabilished regulations, so deviations in the process of trade liberalization that press domestic indrusties will likely to take place. Therefore, it is necessary to have safety actions to actualize mutual benefits in international trade. There are many cases of safety actions conducted by many countries such as Argentine that implements safety actions to its footwear industries without adapting to WTO regulations which causes the country’s losses. The paper examines the consistency of safeguard regulations in Indonesia with safeguard regulations of WTO and its implementation reviewed from the law effectiveness. The result of the study shows that the safeguard regulations in Indonesia is in accordance with the safeguard regulations of WTO in the normative level, but in the implementation the policy is not done effectively.

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.

Integrated safeguards and the role of the SSAC: an Australian perspective

International Nuclear Information System (INIS)

Carlson, John

1998-01-01

'Classical' safeguards retain a strong emphasis on facility-based 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 recognised as a major shortcoming in the classical safeguards system, and major efforts are being made to establish the Agency's capabilities in this regard. Current priorities include, ensuring the wide-spread conclusion of individual Additional Protocols so the Strengthened Safeguards System enters into general application without delay, and continuing the development of new methodologies - including associated quality assurance and evaluation. A major theme in current safeguards thinking is integration, the rationalisation of classical safeguards with the new safeguards strengthening measures. The strengthening of the IAEA safeguards system is a matter of the highest priority to Australia. Australia has had a major influence in this process, that is provision of consultancy services to the Agency on new safeguards and analytical techniques, and in the development and field testing of new safeguards technology such as remote surveillance. (Yi, J. H.)

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

Analysis of UREX+1a and Pyroprocessing Technologies from Safeguards Aspects

International Nuclear Information System (INIS)

Musembi, Mutava Victor; Jeong, Seung Young; Kwon, Eun Ha

2013-01-01

Various advanced and more easily safeguard-able reprocessing technologies have been proposed and are currently at different stages of development. This paper briefly analyses two proposed next generation reprocessing technologies, i. e. UREX+1a and pyroprocessing. It goes on to suggest various measures that can be taken to safeguard these technologies against nuclear proliferation. Due to the significant proliferation risks associated with PUREX, more proliferation resistant technologies are required in spent fuel reprocessing. UREX+1a and pyroprocessing can be suitable replacements since Pu is not separated from other TRUs after reprocessing. Implementations of technology specific safeguard measures can help enhance the proliferation resistance of these technologies. Since there is no technology which is foolproof, a MUF uncertainty estimation/quantification technology needs to be developed. These uncertainty estimates can then be used in a safeguards probabilistic risk assessment (PRA) system to quantify the risks associated with a particular reprocessing technology. To further safeguard these technologies, additional safeguard measures are needed for defense in depth. This may include implementation of multiple, independent, and redundant layers of defense such that no single layer, no matter how robust, is solely relied upon. Quantification of safeguard uncertainties related to UREX+1a and pyroprocessing can be used to benchmark these technologies against PUREX and between themselves for policy making

Analysis of UREX+1a and Pyroprocessing Technologies from Safeguards Aspects

Energy Technology Data Exchange (ETDEWEB)

Musembi, Mutava Victor [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Jeong, Seung Young [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of); Kwon, Eun Ha [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2013-10-15

Various advanced and more easily safeguard-able reprocessing technologies have been proposed and are currently at different stages of development. This paper briefly analyses two proposed next generation reprocessing technologies, i. e. UREX+1a and pyroprocessing. It goes on to suggest various measures that can be taken to safeguard these technologies against nuclear proliferation. Due to the significant proliferation risks associated with PUREX, more proliferation resistant technologies are required in spent fuel reprocessing. UREX+1a and pyroprocessing can be suitable replacements since Pu is not separated from other TRUs after reprocessing. Implementations of technology specific safeguard measures can help enhance the proliferation resistance of these technologies. Since there is no technology which is foolproof, a MUF uncertainty estimation/quantification technology needs to be developed. These uncertainty estimates can then be used in a safeguards probabilistic risk assessment (PRA) system to quantify the risks associated with a particular reprocessing technology. To further safeguard these technologies, additional safeguard measures are needed for defense in depth. This may include implementation of multiple, independent, and redundant layers of defense such that no single layer, no matter how robust, is solely relied upon. Quantification of safeguard uncertainties related to UREX+1a and pyroprocessing can be used to benchmark these technologies against PUREX and between themselves for policy making.

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)

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

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

Developing the information management system for safeguards national inspection

Energy Technology Data Exchange (ETDEWEB)

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

2003-10-01

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

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

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

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

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

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

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

Authentication method for safeguards instruments securing data transmission

International Nuclear Information System (INIS)

Richter, B.; Stein, G.; Neumann, G.; Gartner, K.J.

1986-01-01

Because of the worldwide increase in nuclear fuel cycle activities, the need arises to reduce inspection effort by increasing the inspection efficiency per facility. Therefore, more and more advanced safeguards instruments will be designed for automatic operation. In addition, sensoring and recording devices may be well separated from each other within the facility, while the data transmission medium is a cable. The basic problem is the authenticity of the transmitted information. It has to be ensured that no potential adversary is able to falsify the transmitted safeguards data, i.e. the data transmission is secured. At present, predominantly C/S-devices are designed for automatic and remote interrogation. Also in other areas of safeguards instrumentation authentication will become a major issue, in particular, where the facility operator may offer his process instrumentation to be used also for safeguards purposes. In this paper possibilities to solve the problem of authentication are analysed

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)

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.

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

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)

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

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

ABACC: A regional safeguards agency

International Nuclear Information System (INIS)

Palacios, E.

1998-01-01

Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC) was created as a common system of accounting and control. It is based on Bilateral Agreement between the two countries and the agreement with the IAEA. After a few years of experience it might be concluded that a regional system may contribute in many ways to enhance the safeguards system. The most relevant are: to improve the effectiveness and efficiency of safeguards by sending as professionals who are experts in the process involved in installations that are to be inspected; to have much more information on nuclear activities in each of the two countries than available to the IAEA; and to maintain formal and informal channels of communication

Safeguards surveillance equipment and data sharing between IAEA and a member state

International Nuclear Information System (INIS)

Park, Seung Sik

1999-01-01

Efficiency and reliability are two prongs of implementation of safeguards policy. Unattended surveillance is getting wide acceptance through its field trials and technical advances. In achieving goal of safeguards, new safeguards system should provide less intrusiveness than conventional inspection. Unattended surveillance data share will be a major issue among some countries that have own national inspection scheme in place in parallel with international safeguards to check the resources consuming incurred by the repeated installations. Nonetheless, the issue has not been focussed yet among the States concerned, especially for the country like Korea with national inspection in operation. For balanced development in safeguards regime between IAEA and Korea, sharing of unattended surveillance data with SSAC needs to be worked out in conjunction with the joint use of safeguards instruments that is in the process

Safeguards and security deficiencies fulfilled through technology development

International Nuclear Information System (INIS)

Smoot, W.

1996-01-01

The Office of Safeguards and Security (OSS) sponsors research and development activities based on identified field and headquarters customer requirements. Annually, a formal solicitation of safeguards and security user needs is conducted. Currently, there are over 300 valid safeguards and security deficiencies that have been identified. These user needs serve as the basis for formulating the OSS Technology Development Program (TDP). Due to budget constraints, the TDP can only address approximately 47% of these needs in FY 1996. This paper will discuss, in a general sense, the current deficiencies and how the TDP is responding to each. Specifically, the paper will highlight technologies in the areas of Material Control and Accounting, Physical Security, and Information Security. A brief discussion of unfulfilled user requirements will also be presented as a catalyst for leveraging available or developing technologies from other similar programs or from private industry

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

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

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.

Zone approaches to international safeguards of a nuclear fuel cycle

International Nuclear Information System (INIS)

Fishbone, L.G.; Higinbotham, W.A.

1986-01-01

At present the IAEA designs its safeguards approach with regard to each type of nuclear facility so that the safeguards activities and effort are essentially the same for a given type and size of nuclear facility wherever it may be located. Conclusions regarding a State are derived by combining the results of safeguards verifications for the individual facilities within it. The authors have examined safeguards approaches for a State nuclear fuel cycle that take into account the existence of all of the nuclear facilities in the State. They have focused on the fresh-fuel zone of an advanced nuclear fuel cycle, the several facilities of which use or process low-enriched uranium. The intention is to develop an approach which will make it possible to compare the technical effectiveness and the inspection effort for the facility-oriented approach, for the zone approach and for some reasonable intermediate safeguards approaches

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

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

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

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

broaden the IAEA safeguards toolbox, the study recommends that the Agency consider closing potential gaps in safeguards coverage by, among other things: 1) adapting its safeguards measures based on a case-by-case assessment; 2) using more frequent and expanded/enhanced mailbox declarations (ideally with remote transmission of the data to IAEA Headquarters in Vienna) coupled with short-notice or unannounced inspections; 3) putting more emphasis on the collection and analysis of environmental samples at hot cells and waste storage tanks; 4) taking Safeguards by Design into account for the construction of new research reactors and best practices for existing research reactors; 5) utilizing fully all legal authorities to enhance inspection access (including a strengthened and continuing DIV process); and 6) utilizing new approaches to improve auditing activities, verify reactor operating data history, and track/monitor the movement and storage of spent fuel.

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.

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)'

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

Networking of safeguards systems

International Nuclear Information System (INIS)

Chare, P.; Dutrannois, A.; Kloeckner, W.; Swinhoe, M.

1995-01-01

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

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.

Safeguards research at Lawrence Livermore Laboratory

International Nuclear Information System (INIS)

Dunn, D.R.; Huebel, J.G.; Poggio, A.J.

1980-01-01

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

Steps of Ukrainian SSAC to Integrated Safeguards

International Nuclear Information System (INIS)

Lopatin, S.

2010-01-01

Strengthening of SSAC is a necessary condition for application of integrated safeguards. Ukrainian State System has been working since 1994 and passed several stages in its development: At the early stage it allowed us to conclude the first Safeguards Agreement; In 2003 SSAC covered also all nuclear material at locations outside facilities; In 2006 Additional Protocol (AP) entered into force. The significant contribution to strengthening of SSAC has been made by ISSAS mission carried out in Ukraine in 2007. The mission helped us to evaluate the State Safeguards System, provided us recommendations on improving of legislation, in particular to establish the system of personnel training. Cooperation between the IAEA and Ukrainian SSAC is carried out in following directions. Annual meeting of Safeguards Implementation Review Group takes place in Kiev. Participants discuss current tasks or problem issues of Safeguards implementation and work out Action Plan in order to resolve a problem or find a way for improving situation. Ukrainian State inspectors organize and take part in each IAEA inspection and complementary access. Ukraine has got considerable experience in the AP implementation, to a certain extent determined by peculiarities of Ukraine as a former part of a nuclear weapon state. For 5 years we have accumulated a significant amount of AP information and it became a problem to keep track of it. Due to Protocol Reporter software has limited possibilities there was a need to develop additional software for AP information management. The transmission of encrypted data on nuclear materials from surveillance systems installed at all NPPs directly to the IAEA Headquarters has started recently. Since September 2010 the IAEA plans to use these data for drawing conclusion of safeguards implementation that will allow to reduce the number of IAEA inspections to the Ukrainian NPPs. While implementing the AP we got a question about correspondence of efforts spent for

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

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

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)

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

Safeguards and nonproliferation aspects of a dry fuel recycling technology

International Nuclear Information System (INIS)

Pillay, K.K.S.

1993-01-01

Los Alamos National Laboratory undertook an independent assessment of the proliferation potentials and safeguardability of a dry fuel recycling technology, whereby spent pressurized-water reactor (PWR) fuels are used to fuel canadian deuterium uranium (CANDU) reactors. Objectives of this study included (1) the evaluation of presently available technologies that may be useful to safeguard technology options for dry fuel recycling (2) and identification of near-term and long-term research needs to develop process-specific safeguards requirements. The primary conclusion of this assessment is that like all other fuel cycle alternatives proposed in the past, the dry fuel recycle entails prolfferation risks and that there are no absolute technical fixes to eliminate such risks. This study further concludes that the proliferation risks of dry fuel recycling options are relatively minimal and presently known safeguards systems and technologies can be modified and/or adapted to meet the requirements of safeguarding such fuel recycle facilities

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.

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)

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

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)

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

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

Safeguards Accountability Network accountability and materials management

International Nuclear Information System (INIS)

Carnival, G.J.; Meredith, E.M.

1985-01-01

The Safeguards Accountability Network (SAN) is an on-line accountability system used by Rocky Flats Plant to provide accountability control of its nuclear material inventory. The system is also used to monitor and evaluate the use of the nuclear material inventory against programmatic objectives for materials management. The SAN system utilizes two Harris 800 Computers as central processing units. Enhancement plans are currently being formulated to provide automated data collection from process operations on the shop floor and from non-destructive analysis safeguards instrumentation. SAN, discussed in this paper, is an excellent system for basic accountability control of nuclear materials inventories and is a quite useful tool in evaluating the efficient use of nuclear materials inventories at Rocky Flats Plant

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.

Remote monitoring in safeguards: Security of information and enhanced cooperation

International Nuclear Information System (INIS)

Galdoz, Erwin; Calzetta, Osvaldo; Fernández Moreno, Sonia; Llacer, Carlos; Díaz, Gustavo; Vigile, Sebastián; Brunhuber, Christoph

2011-01-01

Unattended systems with remote transmission capabilities (RM) have the potential to improve safeguards efficiency. Moreover, the evolution of technology and the steady growing of nuclear materials subject to control, lead modern safeguards increasingly utilizing unattended equipment with the capability to store relevant data for long periods of time coupled with the option of being remotely accessed and checked. Remote inspection is still a concept under development, but it may end to be a powerful more efficient verification modality in medium term future. An important part of drawing meaningful safeguards conclusions rests on authenticity and reliability of the information on nuclear material and facilities acquired through the various verification activities and measures applied by IAEA and regional safeguards organizations, like ABACC. The increasing utilization of such technology to further optimize safeguards responds to a multifaceted environment where security of information for all relevant parties is of utmost importance. From the point of view of the IAEA and ABACC, the use of any technology for safeguards application, and specially the use of RM, requires to ensure the security of data collected to guarantee the validity and veracity of such information throughout the whole process (e.g., from collecting to reviewing). This is also valid to the SSAC involved in the process. Information security is also relevant for States and Operators. Assurance should be given that the information could not be withdrawn by non-authorized entities and that facility data is also fully secured. Another important aspect related to RM that may also fall in the security aspect of safeguards relevant information that merits further consideration, is the sharing of information between organizations like ABACC and the IAEA as well as the possibility to make this data available for States authorities purposes. This paper discusses three main themes related to RM: (i) the extent

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

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.

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

International Nuclear Information System (INIS)

Reynolds, D.A.

1981-01-01

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

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

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

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

Year 2000 experience with safeguards instruments

International Nuclear Information System (INIS)

Coffing, J.

1999-01-01

Presentation covers the following items concerning the experiences with safeguards instruments related to Y2K issues: initial Y2K evaluation process; improvement of Y2K testing procedure, policy of the Aquila Technologies Group, Inc. The results concerning Y2K evaluation are presented as designed in the manufacturing process in order to assure success

Overview of simulation applications in safeguards systems

International Nuclear Information System (INIS)

Dugan, V.L.

1976-01-01

The objective of society relative to the utilization of the nuclear fuel cycle is to maximize the benefits of the high quality energy which is available and to minimize the total ''costs'' associated with acquiring these benefits. The comparison of the resulting ''benefits'' to the ''costs'' must be sufficiently attractive for society to accept nuclear energy. In this paper a representation of the structure determined by the ''costs'' (economic, socio-political, institutional, environmental, and legal) associated with adversary action against the nuclear industry and with the measures implemented to deter, prevent, or recover from adversary actions (safeguards) is used to illustrate a broad view of a dynamic safeguards system. This system representation is then used to describe the subsystem areas to which simulation techniques are currently being applied and to suggest other areas in which various simulation applications may benefit the safeguards decision process

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

International nuclear safeguards 1994: Vision for the future. V.1

International Nuclear Information System (INIS)

1994-01-01

Since the last IAEA symposium on this subject, held eight years ego in 1986, the world of safeguards has experienced a number of momentous changes which have opened a new period of intensive development in safeguards. The important events were: The discoveries in Iraq during activities under United Nations Security Council resolutions, South Africa's decision to become a party to the Treaty on the Non-Proliferation of Nuclear Weapons (NPT), the IAEA-Argentina-Brazil-ABACC Quadripartite Safeguards Agreement, the break-up of the former USSR into newly independent States, and the problems encountered in the implementation of NPT safeguards in the Democratic People's Republic of Korea. The consequences for international safeguards of these events were presented in papers at this symposium, with special emphasis on verification of a State's declaration as well as on detection of undeclared activities. Other fundamental changes stem from converging relationships between nuclear arms reductions and the civil use of plutonium, and the international debate on the associated issues. Furthermore, the review and extension of the NPT is due in 1995. Events have opened the possibility for ambitious new concepts for verification regimes. These matters were addressed at the symposium in the opening session and in the closing panel discussion. Refs, figs and tabs

Evaluation of excess nuclear materials suitability for international safeguards

International Nuclear Information System (INIS)

Newton, J.W.; White, W.C.; Davis, R.M.; Cherry, R.C.

1996-01-01

President Clinton announced in March 1995 the permanent withdrawal of 200 tons of fissile material from the US nuclear stockpile. This action was made possible by the dramatic reduction in nuclear weapons stockpile size and a desire to demonstrate the US'' commitment to nonproliferation goals. To provide further assurance of that commitment, the US is addressing placement of these materials under International Atomic Energy Agency (IAEA) safeguards. An initial step of this overall assessment was evaluation of the nuclear materials'' suitability for international safeguards. US Department of Energy (DOE) field organizations reviewed a detailed listing of all candidate materials with respect to characterization status, security classification, and acceptability for international safeguards compared to specified criteria. These criteria included form, location, environment and safety considerations, measurability, and stability. The evaluation resulted in broad categorizations of all materials with respect to preparing and placing materials under IAEA safeguards and provided essential information for decisions on the timing for offering materials as a function of materials attributes. A plan is being prepared to determine the availability of these materials for IAEA safeguards considering important factors such as costs, processes and facilities required to prepare materials, and impacts on other programs

Welcome from ESARDA (European Safeguards Research and Development Association)

International Nuclear Information System (INIS)

Van der Meer, K.

2015-01-01

ESARDA, on the one hand being part of that European family and on the other hand working in practice to support peace by the non-proliferation of nuclear weapons, can be considered as a perfect representative of that European peace process. Going now from the European to the global perspective, peace should be our motivating force and this is also expressed in the basis of safeguards: the non-proliferation Treaty. Several articles of the Treaty deal with not developing nuclear weapons and not supporting the development of nuclear weapons by other countries, and one article (Article VI) deals with the general and complete nuclear disarmament. What is ESARDA doing in practice- First we provide a forum to exchange scientific information for the benefit of all safeguards stakeholders. The most important forum is the biannual open ESARDA safeguards symposium that will be held next year from 19-21 May in Manchester. Next to the ESARDA symposia, we coordinate European safeguards research via our ESARDA Working Groups. Also non-members are welcome in these WG as observers. JRC Ispra maintains the ESARDA website that also supports exchange of safeguards information

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)

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

Implications for Advanced Safeguards Derived from PR and PP Case Study Results

Energy Technology Data Exchange (ETDEWEB)

Boyer, Brian D. [Los Alamos National Laboratory, Nuclear Nonproliferation Division, N-4, Safeguards and Security Group, P. O. Box 1663, N-4, Mail Stop E541, Los Alamos, New Mexico 87545 (United States)

2009-06-15

The proliferation resistance and physical protection (PR and PP) working group produced a case study on the Example Sodium Fast Reactor (ESFR). The ESFR is a hypothetical nuclear energy system consisting of four sodium-cooled fast reactors of medium size collocated with an on-site dry fuel storage facility and a spent fuel reprocessing facility using pyro-processing technology. This study revealed how safeguards would be applied at such site consisting of integrated multiple fuel cycle facilities and the implications of what safeguards technology and safeguards concepts would need to be adapted and developed to safeguard successfully this Generation IV nuclear energy system concept. The major safeguards concepts driving our safeguards analysis are timeliness goals and material quantity goals. Because the fresh transuranic (TRU) fuel to be produced in the ESFR fuel fabrication facility contains plutonium, the ESFR will be reprocessing, using in the reactor, and storing material on site that will have IAEA defined 'direct use material' in it with stringent timeliness goals and material quantity goals that drive the safeguards implementation. Specifically, the TRU fresh fuel, pyro-processing in process material, LWR spent fuel sent to the ESFR, and TRU spent fuel will contain plutonium. This material will need to be verified at interim intervals four times per year because the irradiated direct use material, as defined previously, has three-month timeliness goals and 8 kg material quantity goals for plutonium. The TRU in-process material is, of course, irradiated direct-use material because of keeping the plutonium and uranium together with TRU products that should provide a radiation barrier that slows down the ability to reprocess the fuel and by the process if it intrinsically will take major modification to be able to separate plutonium from the uranium and TRU mixture. This is an issue that the ESFR design must answer to state it has valuable

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.

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)

Nuclear fission and nuclear safeguards: Common technologies and challenges

International Nuclear Information System (INIS)

Keepin, G.R.

1989-01-01

Nuclear fission and nuclear safeguards have much in common, including the basic physical phenomena and technologies involved as well as the commitments and challenges posed by expanding nuclear programs in many countries around the world. The unique characteristics of the fission process -- such as prompt and delayed neutron and gamma ray emission -- not only provide the means of sustaining and controlling the fission chain reaction, but also provide unique ''signatures'' that are essential to quantitative measurement and effective safeguarding of key nuclear materials (notably 239 Pu and 235 U) against theft, loss, or diversion. In this paper, we trace briefly the historical emergence of safeguards as an essential component of the expansion of the nuclear enterprise worldwide. We then survey the major categories of passive and active nondestructive assay techniques that are currently in use or under development for rapid, accurate measurement and verification of safe-guarded nuclear materials in the many forms in which they occur throughout the nuclear fuel cycle. 23 refs., 14 figs

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.

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

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

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

Exploratory study on potential safeguards applications for shared ledger technology

Energy Technology Data Exchange (ETDEWEB)

Frazar, Sarah L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jarman, Kenneth D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Joslyn, Cliff A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Kreyling, Sean J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Sayre, Amanda M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Schanfein, Mark J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); West, Curtis L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Winters, Samuel T. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2017-02-07

The International Atomic Energy Agency (IAEA) is responsible for providing credible assurance that countries are meeting their obligations not to divert or misuse nuclear materials and facilities for non-peaceful purposes. To this end, the IAEA integrates information about States’ nuclear material inventories and transactions with other types of data to draw its safeguards conclusions. As the amount and variety of data and information has increased, the IAEA’s data acquisition, management, and analysis processes have greatly benefited from advancements in computer science, data management, and cybersecurity during the last 20 years. Despite these advancements, inconsistent use of advanced computer technologies as well as political concerns among certain IAEA Member States centered on trust, transparency, and IAEA authorities limit the overall effectiveness and efficiency of IAEA safeguards. As a result, there is an ongoing need to strengthen the effectiveness and efficiency of IAEA safeguards while improving Member State cooperation and trust in the safeguards system. These chronic safeguards needs could be met with some emerging technologies, specifically those associated with the digital currency bitcoin.

Integrated software package for nuclear material safeguards in a MOX fuel fabrication facility

International Nuclear Information System (INIS)

Schreiber, H.J.; Piana, M.; Moussalli, G.; Saukkonen, H.

2000-01-01

Since computerized data processing was introduced to Safeguards at large bulk handling facilities, a large number of individual software applications have been developed for nuclear material Safeguards implementation. Facility inventory and flow data are provided in computerized format for performing stratification, sample size calculation and selection of samples for destructive and non-destructive assay. Data is collected from nuclear measurement systems running in attended, unattended mode and more recently from remote monitoring systems controlled. Data sets from various sources have to be evaluated for Safeguards purposes, such as raw data, processed data and conclusions drawn from data evaluation results. They are reported in computerized format at the International Atomic Energy Agency headquarters and feedback from the Agency's mainframe computer system is used to prepare and support Safeguards inspection activities. The integration of all such data originating from various sources cannot be ensured without the existence of a common data format and a database system. This paper describes the fundamental relations between data streams, individual data processing tools, data evaluation results and requirements for an integrated software solution to facilitate nuclear material Safeguards at a bulk handling facility. The paper also explains the basis for designing a software package to manage data streams from various data sources and for incorporating diverse data processing tools that until now have been used independently from each other and under different computer operating systems. (author)

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

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

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.

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

Unattended safeguards instrumentation at centrifuge enrichment plants

International Nuclear Information System (INIS)

Smith, L. Eric; Lebrun, Alain R.; Labella, Rocco

2014-01-01

As global uranium enrichment capacity under international safeguards expands, the International Atomic Energy Agency (IAEA) is challenged to develop effective safeguards approaches at gaseous centrifuge enrichment plants, particularly high‑capacity plants, while working within budgetary constraints. New safeguards approaches should meet the high‑level verification objectives for such facilities (i.e., timely detection of: diversion of declared material, excess production beyond declared amounts, and production of enrichment levels higher than declared), but should also strive for efficiency advantages in implementation, for both the IAEA and operators. Under the Agency’s State- level approach to safeguards implementation, the Agency needs a flexible toolbox of technologies, allowing tailoring of safeguards measures for each individual enrichment facility. In this paper, the potential roles and development status for three different types of unattended measurement instrumentation are discussed. On‑Line Enrichment Monitors (OLEM) could provide continuous enrichment measurement for 100% of the declared gas flowing through unit header pipes. Unattended Cylinder Verification Stations (UCVS) could provide unattended verification of the declared uranium mass and enrichment of 100% of the cylinders moving through the plant, but also apply and verify an ‘NDA Fingerprint’ to preserve verification knowledge on the contents of each cylinder throughout its life in the facility. Sharing of the operator’s load cell signals from feed and withdrawal stations could count all cylinders introduced to the process and provide periodic monitoring of the uranium mass balance for in‑process material. The integration of load cell, OLEM and UCVS data streams offers the possibility for 100% verification of declared cylinder flow, and enables the periodic verification of the declared 235 U mass balance in the plant. These new capabilities would enhance the IAEA�

A uranium enrichment facility safeguards technology based on the separation nozzle process

International Nuclear Information System (INIS)

Bahm, W.; Weppner, J.; Didier, H.J.

1979-01-01

Under the Trilateral Agreement between Brazil, the Federal Republic of Germany and the IAEA an enrichment plant operating on the basis of the separation nozzle process, will be safeguarded under INFCIRC/66/Rev.2. For nuclear materials balancing purposes the plant has been subdivided into 17 key measuring points to assess the nuclear material flow and the nuclear material inventory. Preliminary studies have indicated that the balancing accuracy required for safeguards purposes cannot be achieved by only using the foreseen in-plant measuring systems, since considerable quantities of enriched uranium cannot be covered in this way. This fraction will merely be estimated by the operator and thus cannot be verified by the inspection authorities. The plant components, whose inventories could not be verified in the first estimate of the balancing accuracy referred to above by means of the in-plant measuring systems, also include the low-temperature separators of the cascade shoulder and the product. Assessing and verifying the inventories of these key measuring points is particularly important because of the enrichment (some 3% 235 U for the product) and the relatively large inventory and, hence, the considerable contribution to the balancing inaccuracy. An estimate of the balancing inaccuracy on the basis of the measuring uncertainties to be expected in the light of the present status of technology indicated values between 0.2 and 0.3% relative to the feed flow with semi-annual inventory-taking. However, this is based on the condition that the experiments planned to determine the inventories of cryogenic separators confirm the measuring uncertainties underlying the calculation

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

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

Safeguarding the fuel cycle: Methodologies

International Nuclear Information System (INIS)

Gruemm, H.

1984-01-01

The effectiveness of IAEA safeguards is characterized by the extent to which they achieve their basic purpose - credible verification that no nuclear material is diverted from peaceful uses. This effectiveness depends inter alia but significantly on manpower in terms of the number and qualifications of inspectors. Staff increases will be required to improve effectiveness further, if this is requested by Member States, as well as to take into account new facilities expected to come under safeguards in the future. However, they are difficult to achieve due to financial constraints set by the IAEA budget. As a consequence, much has been done and is being undertaken to improve utilization of available manpower, including standardization of inspection procedures; improvement of management practices and training; rationalization of planning, reporting, and evaluation of inspection activities; and development of new equipment. This article focuses on certain aspects of the verification methodology presently used and asks: are any modifications of this methodology conceivable that would lead to economies of manpower, without loss of effectiveness. It has been stated in this context that present safeguards approaches are ''facility-oriented'' and that the adoption of a ''fuel cycle-oriented approach'' might bring about the desired savings. Many studies have been devoted to this very interesting suggestion. Up to this moment, no definite answer is available and further studies will be necessary to come to a conclusion. In what follows, the essentials of the problem are explained and some possible paths to a solution are discussed

Measurements Matter in Nuclear Safeguards & Security

International Nuclear Information System (INIS)

Aregbe, Y.; Jakopic, R.; Richter, S.; Schillebeeckx, P.; Hult, M.

2015-01-01

The deliverable of any laboratory is a measurement result with stated uncertainty and traceability (ISO/IEC 17025: 2005). Measurement results, particularly in safeguards, have to be accurate, comparable and traceable to a stated reference, preferably to the SI. Results provided by operator-, safeguards- or network laboratories have to be in compliance with specific quality goals for nuclear material and environmental sample analysis. Metrological quality control tools are prerequisites to build up confidence in measurement results that have to be translated into meaningful safeguards conclusions or to demonstrate conformity of findings with declared processes. The European Commission—Joint Research Centre (EC–JRC) has dedicated facilities, laboratories and projects to provide certified nuclear reference materials (CRM), to develop reference methods and to organize inter-laboratory comparisons (ILC) in compliance with ISO Guide 34, ISO17025 and ISO17043, including respective training. Recent examples are: – cooperation with the JAEA to investigate on the application of Neutron Resonance Densitometry (NRD) to quantify the amount of special nuclear material in particlelike debris of melted fuel as formed in the nuclear accident in Fukushima – training in metrology and gamma-ray spectrometry for EURATOM safeguards inspectors – development of uranium reference particle standards under a new EC support task to the IAEA. Currently, the JRC puts major efforts in producing CRMs and conformity assessment tools for “age-dating” of uranium and plutonium samples. They are needed for method validation in determining the date of the last chemical separation of uranium or plutonium from their daughter nuclides. These type of CRMs are not only needed in nuclear safeguards and forensics, but could support in the future a possible new type of “verification mechanism” as part of the Fissile Material Cut-off Treaty (FMCT), since measurements and measurement standards

An analytical laboratory to facilitate international safeguards

International Nuclear Information System (INIS)

Clark, B.E.; Muellner, P.; Deron, S.

1976-01-01

Member States which have concluded safeguards agreements accept safeguards on part or all of their nuclear facilities and nuclear materials. The Agreements enable the Agency to make inspections in order to verify the location, identity, quantity and composition of all safeguarded nuclear material. The independent analysis of samples of safeguards material is an essential part of the verification process. A new analytical laboratory has been made available to the Agency by the Austrian Government. This facility is staffed by the Agency with scientists and technicians from five Member States. Design criteria for the laboratory were defined by the Agency. Construction was carried out under the project management of the Oesterreichische Studiengesellschaft fuer Atomenergie Ges.m.b.H. Scientific equipment was procured by the Agency. Samples of feed and product material from the nuclear fuel cycle will constitute the main work load. Irradiated and unirradiated samples of uranium, plutonium and mixtures of both will be analysed for concentration and isotopic composition. Since highly diluted solutions of spent fuel will be the most active beta-gamma samples, shielded and remote manipulation facilities are not necessary. Ptentiometry, mass spectrometry and coulometry are the main techniques to be employed. Gravimetry, alpha and gamma spectrometry and emission spectroscopy will also be utilized as required. It is not intended that this laboratory, should carry the whole burden of the Agency's safeguards analytical work, but that it should function as a member of a network of international laboratories which has been set up by the Agency for this purpose. (author)

All-Source Information Acquisition and Analysis in the IAEA Department of Safeguards

International Nuclear Information System (INIS)

Ferguson, Matthew; Norman, Claude

2010-01-01

All source information analysis enables proactive implementation of in-field verification activities, supports the State Evaluation process, and is essential to the IAEA's strengthened safeguards system. Information sources include State-declared nuclear material accounting and facility design information; voluntarily supplied information such as nuclear procurement data; commercial satellite imagery; open source information and information/results from design information verifications (DIVs), inspections and complementary accesses (CAs). The analysis of disparate information sources directly supports inspections, design information verifications and complementary access, and enables both more reliable cross-examination for consistency and completeness as well as in-depth investigation of possible safeguards compliance issues. Comparison of State-declared information against information on illicit nuclear procurement networks, possible trafficking in nuclear materials, and scientific and technical information on nuclear-related research and development programmes, provides complementary measures for monitoring nuclear developments and increases Agency capabilities to detect possible undeclared nuclear activities. Likewise, expert analysis of commercial satellite imagery plays a critical role for monitoring un-safeguarded sites and facilities. In sum, the combination of these measures provides early identification of possible undeclared nuclear material or activities, thus enhancing deterrence of safeguards system that is fully information driven, and increasing confidence in Safeguards conclusions. By increasing confidence that nuclear materials and technologies in States under Safeguards are used solely for peaceful purposes, information-driven safeguards will strengthen the nuclear non-proliferation system. Key assets for Agency collection, processing, expert analysis, and integration of these information sources are the Information Collection and Analysis

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

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.

Safeguards for a nuclear weapon convention

International Nuclear Information System (INIS)

Fischer, D.

1999-01-01

An NDT presupposes a fundamental commitment by all parties to its final objective and hence requires a high and sustained level of confidence amongst all states concerned. The appropriate format for an Nuclear Disarmament Treaty (NDT) would probably be a multilateral treaty open to all states. The treaty must necessarily include the five nuclear weapon states and a procedure would have to be found for securing the ratification of the threshold states without conferring upon them the status of nuclear weapon states. While the IAEA may well be able to carry out the safeguards tasks required by an NDT it would probably be necessary to establish a new international organization to verify the elimination of all nuclear weapons. The experience of UNSCOM and the IAEA in Iraq, and of the IAEA in the DPRK, have shown how difficult the verification of international obligations is in the absence of a commitment to disarm, while the experience of the INF and START treaties, and of the IAEA in South Africa have shown how much simpler it is when the parties concerned are fully committed to the process. Verifying and safeguarding an NDT would be largely an extrapolation of activities already carried out by the nuclear weapon states under the INF and START treaties and by the IAEA in the routine application of safeguards as well as in its less routine work in Iraq, South Africa and the DPRK. Both the verification and safeguarding tasks would be made very much easier if it were possible to bring down to a few hundred the number of nuclear warheads remaining in the hands of any avowed nuclear weapon state, and to conclude a cutoff convention. Experience is needed to show whether the additional safeguards authority accorded to the IAEA by 'programme 93+2' will enable it to effectively safeguard the facilities that would be decommissioned as a result of an NDT and those that would remain in operation to satisfy civilian needs. Subject to this rider and on condition that the IAEA

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

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

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

Improving technical support to IAEA safeguards

International Nuclear Information System (INIS)

Rundquist, D.

1986-01-01

Changes present new safeguards challenges and require that the entire safeguards process become more efficient. A development process has evolved at the Agency that aids in matching appropriate technology to the needs, primarily through the mechanism of voluntary Member States Support Programme, which gives IAEA access to many of the worlds finest nuclear laboratories. The function of these programs is discussed in this article with particular emphasis on the Agency's co-ordination role. Besides a description of the Member States Support Programme the problems involved (coordination and communication aspects) as well as the results achieved are indicated. The support is categorized under the following headlines: 1) Information and expertise; 2) Instrumentation, methods and techniques; 3) Training; 4) Test and calibration facilities. As mentioned in the article Member States also benefit from the Support Programme. Other means of technical support such as multi-national co-operation programmes and bilateral research agreements are mentioned

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

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

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)

Japan-IAEA Workshops on Advanced Safeguards for Future Nuclear Fuel Cycles

International Nuclear Information System (INIS)

Hoffheins, B.; Hori, M.; Suzuki, M.; Kuno, Y.; Kimura, N.; Naito, K.; Hosoya, M.; Khlebnikov, N.; Whichello, J.; Zendel, M.

2010-01-01

Beginning in 2007, the Japan Atomic Energy Agency (JAEA) and the International Atomic Energy Agency (IAEA) Department of Safeguards initiated a workshop series focused on advanced safeguards technologies for the future nuclear fuel cycle (NFC). The goals for these workshops were to address safeguards challenges, to share implementation experiences, to discuss fuel cycle plans and promising research and development, and to address other issues associated with safeguarding new fuel cycle facilities. Concurrently, the workshops also served to promote dialog and problem solving, and to foster closer collaborations for facility design and planning. These workshops have sought participation from IAEA Member States' support programmes (MSSP), the nuclear industry, R and D organizations, state systems of accounting and control (SSAC), regulators and inspectorates to ensure that all possible stakeholder views can be shared in an open process. Workshop presentations have covered, inter alia, national fuel cycle programs and plans, research progress in proliferation resistance (PR) and safeguardability, approaches for nuclear measurement accountancy of large material throughputs and difficult to access material, new and novel radiation detectors with increased sensitivity and automation, and lessons learned from recent development and operation of safeguards systems for complex facilities and the experiences of integrated safeguards (IS) in Japan. Although the title of the workshops presumes an emphasis on technology, participants recognized that early planning and organization, coupled with close cooperation among stakeholders, that is, through the application of 'Safeguards by Design' (SBD) processes that include nuclear safety and security coordination, 'Remote Inspections' and 'Joint-Use of Equipment (JUE)' would be required to enable more successful implementations of safeguards at future NFC facilities. The needs to cultivate the future workforce, effectively preserve

The development and function of the IAEA's safeguards information system

International Nuclear Information System (INIS)

Dell'Acqua, F.; Gmelin, W.; Issaev, L.; Hough, G.; Nardi, J.

1981-01-01

The history of the creation and development of ISIS (International Safeguards Information System), a system for processing information received from Safeguards inspectors about both NPT and non-NPT states, is described. The main procedures for the evaluation of information received from inspectors are also described. ISIS was created on the basis of a commercially available Adaptable DAta-BAse Management System (ADABAS). At the outset, the main efforts of ISIS were devoted to processing the information reported by individual states themselves. The processing of this information fell into three stages: the putting of the information into an intermediate file, then loading the data into logical files, and the quality control of the information. The purpose and motives behind the creation of the new system GULUS (Generalized User Load and Update System) are described, together with its main characteristics. This system is an additional tool for the processing of information provided by inspectors and available even to the not very qualified user. The quick growth of the volume of Safeguards information required more computer power and motivated the buying of a new computer (IBM 3033) which permits the further development of ISIS

Deference and Due Process

OpenAIRE

Vermeule, Cornelius Adrian

2015-01-01

In the textbooks, procedural due process is a strictly judicial enterprise; although substantive entitlements are created by legislative and executive action, it is for courts to decide independently what process the Constitution requires. The notion that procedural due process might be committed primarily to the discretion of the agencies themselves is almost entirely absent from the academic literature. The facts on the ground are very different. Thanks to converging strands of caselaw ...

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

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)

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

Safeguards and security requirements for weapons plutonium disposition in light water reactors

International Nuclear Information System (INIS)

Thomas, L.L.; Strait, R.S.

1994-10-01

This paper explores the issues surrounding the safeguarding of the plutonium disposition process in support of the United States nuclear weapons dismantlement program. It focuses on the disposition of the plutonium by burning mixed oxide fuel in light water reactors (LWR) and addresses physical protection, material control and accountability, personnel security and international safeguards. The S and S system needs to meet the requirements of the DOE Orders, NRC Regulations and international safeguards agreements. Experience has shown that incorporating S and S measures into early facility designs and integrating them into operations provides S and S that is more effective, more economical, and less intrusive. The plutonium disposition safeguards requirements with which the US has the least experience are the implementation of international safeguards on plutonium metal; the large scale commercialization of the mixed oxide fuel fabrication; and the transportation to and loading in the LWRs of fresh mixed oxide fuel. It is in these areas where the effort needs to be concentrated if the US is to develop safeguards and security systems that are effective and efficient

AUTOMATED PROCESS MONITORING: APPLYING PROVEN AUTOMATION TECHNIQUES TO INTERNATIONAL SAFEGUARDS NEEDS

International Nuclear Information System (INIS)

O'Hara, Matthew J.; Durst, Philip C.; Grate, Jay W.; Devol, Timothy A.; Egorov, Oleg; Clements, John P.

2008-01-01

Identification and quantification of specific alpha- and beta-emitting radionuclides in complex liquid matrices is highly challenging, and is typically accomplished through laborious wet chemical sample preparation and separations followed by analysis using a variety of detection methodologies (e.g., liquid scintillation, gas proportional counting, alpha energy analysis, mass spectrometry). Analytical results may take days or weeks to report. Chains of custody and sample security measures may also complicate or slow the analytical process. When an industrial process-scale plant requires the monitoring of specific radionuclides as an indication of the composition of its feed stream or of plant performance, radiochemical measurements must be fast, accurate, and reliable. Scientists at Pacific Northwest National Laboratory have assembled a fully automated prototype Process Monitor instrument capable of a variety of tasks: automated sampling directly from a feed stream, sample digestion/analyte redox adjustment, chemical separations, radiochemical detection and data analysis/reporting. The system is compact, its components are fluidically inter-linked, and analytical results could be immediately transmitted to on- or off-site locations. The development of a rapid radiochemical Process Monitor for 99Tc in Hanford tank waste processing streams, capable of performing several measurements per hour, will be discussed in detail. More recently, the automated platform was modified to perform measurements of 90Sr in Hanford tank waste stimulant. The system exemplifies how automation could be integrated into reprocessing facilities to support international nuclear safeguards needs

Coordinated safeguards for materials management in a uranium--plutonium nitrate-to-oxide coconversion facility: Coprecal

International Nuclear Information System (INIS)

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

1979-02-01

This report describes the conceptual design of an advanced materials-management system for safeguarding special nuclear materials in a uranium--plutonium nitrate-to-oxide coconversion facility based on the Coprecal process. Design concepts are presented for near real-time (dynamic) accountability by forming dynamic materials balances from information provided by chemical and nondestructive analyses and from process-control instrumentation. Modeling and simulation techniques are used to compare the sensitivities of proposed dynamic materials accounting strategies to both abrupt and protracted diversion. The safeguards implications of coconversion as well as some unique features of the reference process are discussed and design criteria are identified to improve the safeguardability of the Coprecal coconversion process

Strengthening of Organizational Infrastructure for Meeting IAEA Nuclear Safeguards Obligations: Bangladesh Perspective

International Nuclear Information System (INIS)

Mollah, A.S.

2010-01-01

Safeguards are arrangements to account for and control the use of nuclear materials. This verification is a key element in the international system which ensures that uranium in particular is used only for peaceful purposes. The only nuclear reactor in Bangladesh achieved critically on September 14, 1986. Reactor Operation and Maintenance Unit routinely carries out certain international obligations which need to undertake as signatory of different treaties, agreements and protocols in the international safeguards regime. Pursuant to the relevant articles of these agreements/protocols, the reactor and associated facilities of Bangladesh (Facility code: BDA- and BDZ-) are physically inspected by the designated IAEA safeguards inspectors. The Bangladesh Atomic Energy Commission (BAEC) has recently created a new division called 'Nuclear Safeguards and Security Division' for enhancing the safeguards activities as per international obligations. This division plays a leading role in the planning, implementation, and evaluation of the BAEC's nuclear safeguards and nuclear security activities. This division is actively working with USDOE, IAEA and EU to enhance the nuclear safeguards and security activities in the following areas: - Analysis of nuclear safeguards related reports of 3 MW TRIGA Mark-II research reactor; - Upgrading of physical protection system of 3 MW TRIGA Mark-II research reactor, gamma irradiation facilities, central radioactive storage and processing facility and different radiation oncology facilities of Bangladesh under GTRI programme; - Supervision for installation of radiation monitoring system of the Chittagong port under USDOE Megaports Initiative Programmes for detection of illicit trafficking of nuclear and radioactive materials; - Development of laboratory capabilities for analysis of nuclear safeguards related samples; - Planning for development of organizational infrastructure to carry out safeguards related activities under IAEA different

Safeguards issues of long-term waste management at DOE sites

International Nuclear Information System (INIS)

Pillay, K.K.S.

1992-06-01

Waste management at US Department of Energy (DOE) sites is not often regarded as a safeguard-sensitive step in the nuclear fuel cycle because the material concerned is relatively unattractive for diversion or theft. However, the accumulation of large amounts of fissile materials in wastes over a period of time can be a safeguards concern. One estimate shows that high-level and transuranic wastes and some miscellaneous radioactive materials at DOE sites may contain as much as 15 Mt of fissile materials. In the context of present US strategies for the disposal of these radioactive wastes, this study identifies safeguards issues relevant to proposed scenarios for the long-term management and permanent disposal of the above-mentioned waste forms in geologic repositories. This study points out areas of concern and the need to examine the issues before the wastes are processed for geologic disposal. Good waste management practices may offer unique opportunities to address the safeguards issues identified here. A judicious approach to examining the safeguards requirements of waste disposal programs may also contribute to DOE's new effort to establish and maintain public confidence in its environmental restoration programs

5 CFR 732.301 - Due process.

Science.gov (United States)

2010-01-01

... 5 Administrative Personnel 2 2010-01-01 2010-01-01 false Due process. 732.301 Section 732.301...) NATIONAL SECURITY POSITIONS Due Process and Reporting § 732.301 Due process. When an agency makes an... any determination. (b) Comply with all applicable administrative due process requirements, as provided...

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.

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

The future for safeguards technology

International Nuclear Information System (INIS)

Zykov, S.

2013-01-01

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

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)

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

Safeguards by Design at the Encapsulation Plant in Finland

International Nuclear Information System (INIS)

Ingegneri, M.; Baird, K.; Park, W.-S.; Coyne, J.M.; Enkhjin, L.; Chew, L.S.; Plenteda, R.; Sprinkle, J.; Yudin, Y.; Ciuculescu, C.; Koutsoyannopoulos, C.; Murtezi, M.; Schwalbach, P.; Vaccaro, S.; Pekkarinen, J.; Thomas, M.; Zein, A.; Honkamaa, T.; Hamalainen, M.; Martikka, E.; Moring, M.; Okko, O.

2015-01-01

Finland has launched a spent fuel disposition project to encapsulate all of its spent fuel assemblies and confine the disposal canisters in a deep geological repository. The construction of the underground premises started several years ago with the drilling, blasting and reinforcement of tunnels and shafts to ensure the safe deep underground construction and disposal techniques in the repository, while the design of the encapsulation plant (EP) enters the licencing phase preliminary to its construction. The spent fuel assemblies, which have been safeguarded for decades at the nuclear power plants, are going to be transported to the EP, loaded into copper canisters and stored in underground tunnels where they become inaccessible after backfilling. Safeguards measures are needed to ensure that final spent fuel verification is performed before its encapsulation and that no nuclear material is diverted during the process. This is an opportunity for the inspectorates to have the infrastructure necessary for the safeguards equipment incorporated in the design of the encapsulation plant before licencing for construction occurs. The peculiarity of this project is that it is going to run for more than a century. Therefore, significant changes are to be expected in the technical capabilities available for implementing safeguards (e.g., verification techniques and instruments), as well as in the process itself, e.g., redesign for the encapsulation of future fuel types. For these reasons a high degree of flexibility is required in order to be able to shift to different solutions at a later stage while minimizing the interference with the licencing process and facility operations. This paper describes the process leading to the definition of the technical requirements by IAEA and Euratom to be incorporated in the facility's design. (author)

International safeguards for a modern MOX [mixed-oxide] fuel fabrication facility

International Nuclear Information System (INIS)

Pillay, K.K.S.; Stirpe, D.; Picard, R.R.

1987-03-01

Bulk-handling facilities that process plutonium for commercial fuel cycles offer considerable challenges to nuclear materials safeguards. Modern fuel fabrication facilities that handle mixed oxides of plutonium and uranium (MOX) often have large inventories of special nuclear materials in their process lines and in storage areas for feed and product materials. In addition, the remote automated processing prevalent at new MOX facilities, which is necessary to minimize radiation exposures to personnel, tends to limit access for measurements and inspections. The facility design considered in this study incorporates all these features as well as state-of-the-art measurement technologies for materials accounting. Key elements of International Atomic Energy Agency (IAEA) safeguards for such a fuel-cycle facility have been identified in this report, and several issues of primary importance to materials accountancy and IAEA verifications have been examined. We have calculated detection sensitivities for abrupt and protracted diversions of plutonium assuming a single materials balance area for all processing areas. To help achieve optimal use of limited IAEA inspection resources, we have calculated sampling plans for attributes/variables verification. In addition, we have demonstrated the usefulness of calculating σ/sub (MUF-D)/ and detection probabilities corresponding to specified material-loss scenarios and resource allocations. The data developed and the analyses performed during this study can assist both the facility operator and the IAEA in formulating necessary safeguards approaches and verification procedures to implement international safeguards for special nuclear materials

International safeguards for a modern MOX (mixed-oxide) fuel fabrication facility

Energy Technology Data Exchange (ETDEWEB)

Pillay, K.K.S.; Stirpe, D.; Picard, R.R.

1987-03-01

Bulk-handling facilities that process plutonium for commercial fuel cycles offer considerable challenges to nuclear materials safeguards. Modern fuel fabrication facilities that handle mixed oxides of plutonium and uranium (MOX) often have large inventories of special nuclear materials in their process lines and in storage areas for feed and product materials. In addition, the remote automated processing prevalent at new MOX facilities, which is necessary to minimize radiation exposures to personnel, tends to limit access for measurements and inspections. The facility design considered in this study incorporates all these features as well as state-of-the-art measurement technologies for materials accounting. Key elements of International Atomic Energy Agency (IAEA) safeguards for such a fuel-cycle facility have been identified in this report, and several issues of primary importance to materials accountancy and IAEA verifications have been examined. We have calculated detection sensitivities for abrupt and protracted diversions of plutonium assuming a single materials balance area for all processing areas. To help achieve optimal use of limited IAEA inspection resources, we have calculated sampling plans for attributes/variables verification. In addition, we have demonstrated the usefulness of calculating sigma/sub (MUF-D)/ and detection probabilities corresponding to specified material-loss scenarios and resource allocations. The data developed and the analyses performed during this study can assist both the facility operator and the IAEA in formulating necessary safeguards approaches and verification procedures to implement international safeguards for special nuclear materials.

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

Safeguards decision making in the public and regulatory environment, and the potential role of quantitative approaches

International Nuclear Information System (INIS)

Sherr, T.S.

1981-01-01

This paper briefly examines the nature of the safeguards program's objectives and constraints, and the inherent limitations on comprehensive quantification. It discusses the nature of the public and regulatory processes employed in safeguards decision making, and examines their implications regarding the potential role of quantitative approaches to safeguards policy and operational decision making

45 CFR 310.15 - What are the safeguards and processes that comprehensive Tribal IV-D agencies must have in place...

Science.gov (United States)

2010-10-01

... 45 Public Welfare 2 2010-10-01 2010-10-01 false What are the safeguards and processes that... IV-D Systems and Office Automation? 310.15 Section 310.15 Public Welfare Regulations Relating to... AND OFFICE AUTOMATION Requirements for Computerized Tribal IV-D Systems and Office Automation § 310.15...

Strengthening safeguards information evaluation

International Nuclear Information System (INIS)

Harry, J.; Hudson, P.

2001-01-01

The strengthening of safeguards should not be limited to the verification of explicit declarations made by the States. Additional information should guide the IAEA to set priorities for further investigations. Not only all aspects of the State's nuclear programme, including the application of safe, secure and transparent nuclear management, but also the level of compliance with other verifiable treaties, political motivation, economic capabilities, international relations and ties, co-operative attitude to safeguards, and general openness and transparency should be included. The evaluation of the diverse forms of information from different sources requires new reliable processes that will result in a high credibility and detection probability. The IAEA uses the physical model for the evaluation of the technical information, and proposed also Fuzzy Logic, or Calculation with Words, to handle the information. But for the evaluation it is questioned whether fuzziness could lead to a crisp judgement. In this paper an objective method of information evaluation is proposed, which allows to integrate different kinds of information and to include calibration and tests in the establishment of the evaluation process. This method, Delta, uses elicitation of a syndicate of experienced inspectors to integrate obvious indicators together with apparently innocent indicators, into a database that forms the core of the evaluation process. Nominal or ordinal scales could be applied to come to an objective and quantifiable result. Experience with this method can in the course of time result in predictive conclusions. 9 refs

The processing and evaluation of new information for strengthened safeguards

International Nuclear Information System (INIS)

Nilsson, A.

1999-01-01

The framework of safeguard activities of the IAEA from the viewpoint of informanagement is described. As methodology, major sources of information are, member state supplied information, information obtained by the Agency through its verification activity, and open source information. Software tools are provided to retrieve and to filter information for storage. Organizational structure of the Agency's information activities, and the changing roles of the inspectors are also described. (Yamamoto, A.)

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

IAEA safeguards and non-proliferation

International Nuclear Information System (INIS)

Harry, R.J.S.

1995-02-01

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

IAEA safeguards and non-proliferation

Energy Technology Data Exchange (ETDEWEB)

Harry, R J.S.

1995-02-01

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

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

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

Simulation enabled safeguards assessment methodology

International Nuclear Information System (INIS)

Bean, Robert; Bjornard, Trond; Larson, Tom

2007-01-01

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

Simulation Enabled Safeguards Assessment Methodology

International Nuclear Information System (INIS)

Robert Bean; Trond Bjornard; Thomas Larson

2007-01-01

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

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

International Nuclear Information System (INIS)

Smolej, M.

1999-01-01

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

Termination of international safeguards on nuclear material discards: An IAEA update

International Nuclear Information System (INIS)

Larrimore, J.A.

1995-01-01

The IAEA adopted a policy for termination of international safeguards on measured discards in mid-1994. The policy addresses a broad range of termination of safeguards on nuclear material in waste with a focus on conditioned waste arising from reprocessing. The safeguards relevant aspects of waste handling up to the point of termination must be approved, and a determination made that the waste type, form of conditioning and nuclear material concentration satisfy specific criteria. In addition, the State where the terminated waste will be stored is requested to notify the IAEA of future movement or processing of the waste. Cases of international transfers of conditioned waste are also addressed

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.

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.)

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)

Fuel cycle of nuclear power plants and safeguards system of nuclear weapon nonproliferation

International Nuclear Information System (INIS)

Malek, Z.

1980-10-01

The international safeguard system of nuclear weapon nonproliferation and the IAEA safeguard system are briefly described. In Czechoslovakia, a decree was issued in 1977 governing the accounting for and control of nuclear materials. The contents of the decree are presented. Described are computer processing of accounting data, technical criteria for the safeguard system application, containment and inspection in the IAEA safeguard system. The method is shown of the control of and accounting for nuclear materials in nuclear power plants and in fuel manufacturing, reprocessing and enrichment plants. Nondestructive and destructive methods of nuclear materials analysis are discussed. Nondestructive methods used include gamma spectrometry, neutron techniques, X-ray fluores--cence techniques. (J.P.)

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

IAEA has stated the importance of enhancing cooperation with SSAC. Therefore, Japan has developed the Integrated Safeguards Information System for enhancing confidence in compliance with the national obligation under the safeguards agreement and the additional protocol. Japan already established the National System including national inspections with NDA and DA verification functions and evaluation of data obtained from national inspections and has maintained the National System of safeguards as a SSAC in accordance with the safeguards agreement. Nuclear Material Control Center (NMCC) is engaged in national safeguards activities as designated organization of national inspectorate and information treatment including safeguards data analysis. Recently, purpose of IAEA's safeguards activities may shift to detection of proliferation based on plausible proliferation paths from detection of diversion by certain material accountancy measures. Major safeguards activities of IAEA have changed from quantitative aspects to qualitative them. As supplements for declining the quantitative measures such as the activities based on the safeguards criteria the IAEA would expect the SSAC functions for maintaining the activities of quantitative manners. Japan believes that the State's responsibility for enhancing cooperation between the National System and the IAEA must assure the confidence level of correctness and completeness of the State declarations with accurate and precise accountability as findings from SSAC. Japan has started the development of the strengthened and autonomous national system namely the Integrated safeguards Information System for Japan (ISIS-J) in order to fulfil our responsibility. Japan would seek to improve quality of information including nuclear material accounting data as well as expanded declaration relevant to nuclear activities in Japan, and to increase abilities for explaining safeguards relevant events in Japan. The enhanced findings could include

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

Scientific and technical information as a source for IAEA safeguards state evaluation

Energy Technology Data Exchange (ETDEWEB)

Barletta, M.; Feldman, Y.; Ferguson, M. [International Atomic Energy Agency, Vienna (Austria)

2014-07-01

The IAEA Department of Safeguards is continually working to refine its methodologies and procedures for the analysis of information relevant to the evaluation of the nuclear fuel cycle in States that have safeguards agreements with the IAEA. This analysis is required to achieve an understanding of States' nuclear-related activities against which a State's declarations are evaluated for correctness as well as completeness, and to provide credible assurances on the peaceful uses of nuclear material in the State. To achieve this end, diversification of sources and comparison for consistency among available information is essential to ensure an accurate assessment of a State's nuclear activities. Open sources of information on scientific and technical (S&T) developments and research provide the Department of Safeguards with an enhanced basis to evaluate the technical capabilities of States. These information sources are regularly and systematically assessed to provide information about industrial capabilities, patenting activities and research and development activities in States as reflected through published scientific and technical literature. Using such sources, in addition to other, long-established safeguards information sources, helps the IAEA to draw soundly-based safeguards conclusions. The utility of this category of information in terms of the State evaluation process lies primarily in the comparison with other sources of information, especially State-declared information, and in the assessment of consistency of all safeguards-relevant information regarding nuclear fuel cycle technologies and activities in a State. The current paper aims to describe the use of S&T literature, how information from different sources is consolidated, how it is analysed and how it contributes in the overall process of State evaluation in the IAEA Department of Safeguards. (author)

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

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

IAEA safeguards information system re-engineering project (IRP)

International Nuclear Information System (INIS)

Whitaker, G.; Becar, J.-M.; Ifyland, N.; Kirkgoeze, R.; Koevesd, G.; Szamosi, L.

2007-01-01

The Safeguards Information System Re-engineering Project (IRP) was initiated to assist the IAEA in addressing current and future verification and analysis activities through the establishment of a new information technology framework for strengthened and integrated safeguards. The Project provides a unique opportunity to enhance all of the information services for the Department of Safeguards and will require project management 'best practices' to balance limited funds, available resources and Departmental priorities. To achieve its goals, the Project will require the participation of all stakeholders to create a comprehensive and cohesive plan that provides both a flexible and stable foundation for address changing business needs. The expectation is that high quality integrated information systems will be developed that incorporate state-of-the-art technical architectural standards, improved business processes and consistent user interfaces to store various data types in an enterprise data repository which is accessible on-line in a secure environment. (author)

Task team approach to safeguards and security designs

International Nuclear Information System (INIS)

Zack, N.R.; Wilkey, D.D.

1991-01-01

In 1987, a U.S. department of Energy (DOE) supported task team was organized at the request of the DOE Idaho Field Office (DOE-ID) to provide support for safeguards and security (S and S) designs of the Special Isotope Separation (SIS) facility. Prior to deferral of the project, the SIS facility was to be constructed at the Idaho National Engineering Laboratory (INEL) to produce weapons grade plutonium from DOE owned fuel grade plutonium. The task team was assembled to provide the resources necessary to assure that S and S considerations were included as an integral part of the design of the facility, and that SIS designs would take advantage of available technology in the areas of physical security, measurements, accountability, and material and personnel tracking. The task team included personnel from DOE/Office of Safeguards and Security (DOE-OSS), DOE-ID, DOE contractors, and the national laboratories providing a wide range of expertise and experience. This paper reports that the team reviewed proposed designs and provided recommendations for safeguards and security features in each stage of the design process. The value of this approach to safeguards and security designs will be discussed with respect to benefits, lessons learned, and recommendations for future applications

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

Safeguards and security by design (SSBD) for the domestic threat. Theft and sabotage

International Nuclear Information System (INIS)

DeMuth, Scott; Mullen, Mark; Pan, Paul

2011-01-01

In recent years, the Safeguards by Design (SBD) concept has received significant interest with respect to international (IAEA) safeguards objectives. However, less attention has been focused on the equally important topic of domestic (or national) Safeguards and Security by Design (SSBD), which addresses domestic requirements for material control and accounting (MC and A) and for physical protection, such as those of the Nuclear Regulatory Commission (NRC) in the United States. While international safeguards are concerned with detecting State diversion of nuclear material from peaceful uses to nuclear explosives purposes, domestic material control and accounting (MC and A) and physical protection are focused on non-State theft and sabotage. The International Atomic Energy Agency (IAEA) has described the Safeguards by Design (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.' This same concept is equally applicable to SSBD for domestic requirements. The United States Department of Energy (DOE) has initiated a project through its Office of Nuclear Energy (NE), and more specifically its Materials Protection, Accounting, and Control Technologies (MPACT) program, to develop a domestic SSBD discipline and methodology in parallel with similar efforts for international safeguards sponsored by the DOE Next Generation Safeguards Initiative (NGSI) and the IAEA. This paper identifies the key domestic safeguards and security requirements (i.e., MC and A and physical protection) and explains how and why Safeguards and Security by Design (SSBD) is important and beneficial for the design of future US nuclear energy systems. (author)

Safeguards and security by design (SSBD) for the domestic threat - theft and sabotage

International Nuclear Information System (INIS)

Demuth, Scott F.; Mullen, Mark

2011-01-01

Safeguards by Design (SBD) is receiving significant interest with respect to international safeguards objectives. However, less attention has been focused on the equally important topic of domestic Safeguards and Security by Design (SSBD), which addresses requirements such as those of the Nuclear Regulatory Commission (NRC) in the United States. While international safeguards are concerned with detecting State diversion of nuclear material from peaceful to nuclear explosives purposes, domestic Material Protection, Control and Accounting measures (MPC and A) are focused on non-State theft and sabotage. The International Atomic Energy Agency (IAEA) has described the Safeguards by Design (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.' This same concept is equally applicable to SSBD for domestic requirements. The United States Department of Energy (DOE) has initiated a project through its Office of Nuclear Energy (NE) and more specifically its Fuel Cycle Research and Development (FCRD) program, to develop a domestic SSBD discipline and methodology in parallel with similar efforts sponsored by the DOE Next Generation Safeguards Initiative (NGSI) and the IAEA for international safeguards. This activity includes the participation of industry (through DOE-sponsored contracts) and DOE National Laboratories. This paper will identify the key domestic safeguards and security requirements (i.e. MC and A and physical protection) and explain how and why Safeguards and Security by Design (SSBD) is important and beneficial for the design of future US nuclear energy systems.

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

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

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

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

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

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

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

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

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

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

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

Implementation of Safeguards for Romania National LOFs

International Nuclear Information System (INIS)

Popovici, I.

2015-01-01

The safe deployment of nuclear activities in Romania is provided by Law no. 111/1996. The Law was republished based on the provisions of Article II of Law no. 63/2006 for the amendment and addition and was modified and completed by the Law no. 378/2013. The competent national authority in the nuclear field, which has responsibilities of regulation, authorization and control as stipulated in this Law, is the National Commission for Nuclear Activities Control (CNCAN). According to art. 2c), provisions of the Nuclear Law shall apply to production, sitting and construction, supply, leasing, transfer, handling, possession, processing, treatment, use, temporary storage or final disposal, transport, transit, import and export of radiological installations, nuclear and radioactive materials, including nuclear fuel, radioactive waste and ionizing radiation generating devices. With regards to the small holders of nuclear materials, the Romanian legislation takes into account the following safeguards objectives: · Establishing provisions governing the possession, use, transfer, import and export of nuclear materials; · Ensuring the implementation of the safeguards system for accountancy and control of nuclear materials: · Ensuring that all nuclear materials are reported under the provisions of the Safeguards Agreement; · Ensuring that all nuclear activities are declared under the provisions of the Additional Protocol; · Developing and implementing nuclear material accounting and control procedures at all small holders of nuclear materials; · Ensuring training for safeguards staff at all small holders. Based on the provision of Law no. 111/1996 CNCAN has issued a Guidelines for applying of the safeguards by the small holders of nuclear materials from Romania. The guidelines provide specific regulations regarding the movement of the nuclear materials, the accountancy and control of nuclear materials, the containment and surveillance systems for small holders of nuclear

Zone approaches to international safeguards of a nuclear fuel cycle

International Nuclear Information System (INIS)

Fishbone, L.G.; Higinbotham, W.A.

1986-01-01

At present the IAEA designs its safeguards approach with regard to each type of nuclear facility so that the safeguards activities and effort are essentially the same for a given type and size of nuclear facility wherever it may be located. Conclusions regarding a state are derived by combining the results of safeguards verifications for the individual facilities within it. We have examined safeguards approaches for a state nuclear fuel cycle that take into account the existence of all of the nuclear facilities in the state. We have focussed on the fresh-fuel zone of an advanced nuclear fuel cycle, the several facilities of which use or process low-enriched uranium. At one extreme, flows and inventories would be verified at each material balance area. At the other extreme, the flows into and out of the zone and the inventory of the whole zone would be verified. The intention is to develop an approach which will make it possible to compare the technical effectiveness and the inspection effort for the facility-oriented approach, for the zone approach and for some reasonable intermediate safeguards approaches. Technical effectiveness, in these cases, means an estimate of the assurance that all nuclear material has been accounted for

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.

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

Safeguards Implementation Practices Guide on Provision of Information to the IAEA

International Nuclear Information System (INIS)

2016-01-01

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 and is furthered through a common understanding of the respective rights and obligations of States and the IAEA. To address this, in 2012 the IAEA published IAEA Services Series No. 21, Guidance for States Implementing Comprehensive Safeguards Agreements and Additional Protocols, which aimed at enhancing understanding and improving cooperation in safeguards implementation. To meet their safeguards obligations, States may establish different processes and procedures at the national level, and set up their infrastructure to meet their specific needs. Indeed, a variety of approaches are to be expected, owing to differences in the size and complexity of States’ nuclear programmes, their regulatory framework and other factors. 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. This SIP Guide addresses the important topic of the provision of information by States to the IAEA. Declarations by States form the basis for IAEA verification activities, and the quality and timeliness of such declarations impact significantly the efficiency of safeguards implementation. The information contained in the SIP Guides is provided for explanatory purposes and their use is voluntary. 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

A selection of recent achievements and future challenges in safeguards R and D as identified by the European safeguards research and development association

International Nuclear Information System (INIS)

Janssens, W.A.M.; Sevini, F.; Bril, L.V.; Janssens-Maenhout, G.G.A.; Goncalves, J.G.M.; Peerani, P.; Autrusson, B.; Boella, M.; Martikka, E.; Toivonen, H.; Mayer, K.; Rezniczek, A.; Richard, M.; Richter, B.; Stein, G.; Weh, R.

2010-01-01

In the year of its 40. anniversary, ESARDA can look back on a wealth of achievements in the European safeguards area, to which its members have substantially contributed. Also today, ESARDA is more active then ever, both due to an extended partnership (with many new members joining in recent years) and a pro-active attitude to tackle new and upcoming issues through its many Working Groups. ESARDA constitutes today of 9 working groups: Non Destructive Analysis (NDA), Destructive Analysis (DA), Containment and Surveillance (C/S), Verification Technologies and Methodologies (VTM), Implementation of Safeguards (IS), Nuclear Material Accounting and Control Audit Group (NMACAG), Training and Knowledge Management (TKM), Editorial Committee (EDC) and the newly established Novel technologies and approaches (NT/NA). The Fuel Fabrications Plants WG has recently been stopped and part of the activities possibly moved into IS WG. Most of these working groups organise regular meetings in which they discuss the progress, achievements, problems, challenges and future needs for R and D. They jointly work out solutions to problems and stay abreast of the latest safeguards R and D aspects. This paper will provide an overview of some most relevant recent achievements of the ESARDA Working Groups and will provide an insight in the challenges identified for safeguards R and D in the near and medium term future. (authors)

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

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)

Concerns when designing a safeguards approach for the back-end of the Swedish nuclear fuel cycle

International Nuclear Information System (INIS)

Fritzell, Anni

2006-03-01

In Sweden, the construction of an encapsulation plant and a geological repository for the final disposal of spent nuclear fuel is planned to start within the next ten years. Due to Sweden's international agreements on non-proliferation, the Swedish safeguards regime must be extended to include these facilities. The geological repository has some unique features, which present the safeguards system with unprecedented challenges. These features include, inter alia, the long period of time that the facility will contain nuclear material and that the disposed nuclear material will be very difficult to access, implying that physical verification of its presence in the repository is not foreseen. This work presents the available techniques for creating a safeguards system for the backend of the Swedish nuclear fuel cycle. Important issues to consider in the planning and implementation of the safeguards system have been investigated, which in some cases has led to an identification of areas needing further research. The results include three proposed options for a safeguards approach, which have been evaluated on the basis of the safeguards authorities' requirements. Also, the evolution and present situation of the work carried out in connection to safeguards for geological repositories has been compiled

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

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.

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

How the Office of Safeguards and Security Technology development program facilitates safeguarding and securing the DOE complex

International Nuclear Information System (INIS)

Smoot, W.

1995-01-01

The technology development program's (TDP's) mission is to provide technologies or methodologies that address safeguards and security requirements throughout the U.S. DOE complex as well as to meet headquarters' policy needs. This includes developing state-of-the-art technologies or modifying existing technologies in physical security, material control and accountability, information security, and integrated safeguards systems. The TDP has an annual process during which it solicits user requirements from the field. These requirements are analyzed by DOE headquarters and laboratory personnel for technical merit. The requirements are then prioritized at headquarters, and the highest priorities are incorporated into our budget. Although this user-needs process occurs formally once a year, user requirements are accepted at any time. The status of funded technologies is communicated through briefings, programs reviews, and various documents that are available to all interested parties. Participants in several interagency groups allows our program to benefit from what others are doing and to prevent duplications of efforts throughout the federal community. Many technologies are transferred to private industry

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.

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.

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.

Safeguards and security by design support for the next generation nuclear plant project - Progress in safeguards by design (SBD) by the United States National Nuclear Security Administration (NNSA)

International Nuclear Information System (INIS)

Bjornard, T.; Casey Durst, P.

2013-01-01

The Next Generation Nuclear Plant (NGNP) project was authorized by the United States Energy Policy Act of 2005 with the principal objective of designing, licensing, and building a Generation IV nuclear plant capable of producing both high-temperature process heat and electricity. The two candidate NGNP reactor concepts are pebble- and prismatic-fueled high-temperature gas reactors that will be licensed by the U.S. Nuclear Regulatory Commission (NRC). The conceptual design phase of the project was completed in December 2010. This paper summarizes support provided to the NGNP project to facilitate consideration of international safeguards during the design phase, or safeguards by design (SBD). Additional support was provided for domestic safeguards (material control and accounting) and physical protection, or safeguards and security by design (2SBD). The main focus of this paper is on SBD and international safeguards. Included is an overview of the international safeguards guidance contained in guidance reports for SBD. These reports contain guidance and suggestions intended to be useful to the industry design teams, but they do not contain ready-made solutions. Early and frequent interaction of design stakeholders with the International Atomic Energy Agency and the NRC are essential to a successful endeavor. The paper is followed by the slides of the presentation. (author)

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

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

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

Gas centrifuge enrichment plants inspection frequency and remote monitoring issues for advanced safeguards implementation

International Nuclear Information System (INIS)

Boyer, Brian David; Erpenbeck, Heather H.; Miller, Karen A.; Ianakiev, Kiril D.; Reimold, Benjamin A.; Ward, Steven L.; Howell, John

2010-01-01

Current safeguards approaches used by the IAEA at gas centrifuge enrichment plants (GCEPs) need enhancement in order to verify declared low enriched uranium (LEU) production, detect undeclared LEU production and detect high enriched uranium (BEU) production with adequate probability using non destructive assay (NDA) techniques. At present inspectors use attended systems, systems needing the presence of an inspector for operation, during inspections to verify the mass and 235 U enrichment of declared cylinders of uranium hexafluoride that are used in the process of enrichment at GCEPs. This paper contains an analysis of how possible improvements in unattended and attended NDA systems including process monitoring and possible on-site destructive analysis (DA) of samples could reduce the uncertainty of the inspector's measurements providing more effective and efficient IAEA GCEPs safeguards. We have also studied a few advanced safeguards systems that could be assembled for unattended operation and the level of performance needed from these systems to provide more effective safeguards. The analysis also considers how short notice random inspections, unannounced inspections (UIs), and the concept of information-driven inspections can affect probability of detection of the diversion of nuclear material when coupled to new GCEPs safeguards regimes augmented with unattended systems. We also explore the effects of system failures and operator tampering on meeting safeguards goals for quantity and timeliness and the measures needed to recover from such failures and anomalies.

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.

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

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

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

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.

Advanced Nuclear Measurements - Sensitivity Analysis Emerging Safeguards, Problems and Proliferation Risk

International Nuclear Information System (INIS)

Dreicer, J.S.

1999-01-01

During the past year this component of the Advanced Nuclear Measurements LDRD-DR has focused on emerging safeguards problems and proliferation risk by investigating problems in two domains. The first is related to the analysis, quantification, and characterization of existing inventories of fissile materials, in particular, the minor actinides (MA) formed in the commercial fuel cycle. Understanding material forms and quantities helps identify and define future measurement problems, instrument requirements, and assists in prioritizing safeguards technology development. The second problem (dissertation research) has focused on the development of a theoretical foundation for sensor array anomaly detection. Remote and unattended monitoring or verification of safeguards activities is becoming a necessity due to domestic and international budgetary constraints. However, the ability to assess the trustworthiness of a sensor array has not been investigated. This research is developing an anomaly detection methodology to assess the sensor array

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

Verification and the safeguards legacy

International Nuclear Information System (INIS)

Perricos, Demetrius

2001-01-01

; qualitative and quantitative measurements of nuclear material; familiarity and access to sensitive technologies related to detection, unattended verification systems, containment/surveillance and sensors; examination and verification of design information of large and complex facilities; theoretical and practical aspects of technologies relevant to verification objectives; analysis of inspection findings and evaluation of their mutual consistency; negotiations on technical issues with facility operators and State authorities. This experience is reflected in the IAEA Safeguards Manual which sets out the policies and procedures to be followed in the inspection process as well as in the Safeguards Criteria which provide guidance for verification, evaluation and analysis of the inspection findings. The IAEA infrastructure and its experience with verification permitted in 1991 the organization to respond immediately and successfully to the tasks required by the Security Council Resolution 687(1991) for Iraq as well as to the tasks related to the verification of completeness and correctness of the initial declarations in the cases of the DPRK. and of S. Africa. In the case of Iraq the discovery of its undeclared programs was made possible through the existing verification system enhanced by additional access rights, information and application of modern detection technology. Such discoveries made it evident that there was a need for an intensive development effort to strengthen the safeguards system to develop a capability to detect undeclared activities. For this purpose it was recognized that there was need for additional and extended a) access to information, b) access to locations. It was also obvious that access to the Security Council, to bring the IAEA closer to the body responsible for maintenance of international peace and security, would be a requirement for reporting periodically on non-proliferation and the results of the IAEA's verification activities. While the case

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

The U.S./IAEA Workshop on Software Sustainability for Safeguards Instrumentation

Energy Technology Data Exchange (ETDEWEB)

Pepper S. E.; .; Worrall, L.; Pickett, C.; Bachner, K.; Queirolo, A.

2014-08-08

The U.S. National Nuclear Security Administration’s Next Generation Safeguards Initiative, the U.S. Department of State, and the International Atomic Energy Agency (IAEA) organized a a workshop on the subject of ”Software Sustainability for Safeguards Instrumentation.” The workshop was held at the Vienna International Centre in Vienna, Austria, May 6-8, 2014. The workshop participants included software and hardware experts from national laboratories, industry, government, and IAEA member states who were specially selected by the workshop organizers based on their experience with software that is developed for the control and operation of safeguards instrumentation. The workshop included presentations, to orient the participants to the IAEA Department of Safeguards software activities related to instrumentation data collection and processing, and case studies that were designed to inspire discussion of software development, use, maintenance, and upgrades in breakout sessions and to result in recommendations for effective software practices and management. This report summarizes the results of the workshop.

Progress in safeguards by design (SBD) by the United States National Nuclear Security Administration (NNSA)

International Nuclear Information System (INIS)

Long, J.D.

2013-01-01

The IAEA has described the Safeguards by Design (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. Often, international safeguards features are added following completion of the facility design. Earlier consideration of safeguards features has the potential to reduce the need for costly re-designs or retrofits of the facility and can result in a more efficient and effective safeguards design. The U.S. Department of Energy's National Nuclear Security Administration (NNSA) initiated a project in 2008 through its Next Generation Safeguards Initiative (NGSI) to establish a global norm for the use of SBD. The NGSI SBD program is evolving in parallel with a similar effort at the IAEA, while taking into account the IAEA's SBD achievements and future plans. The NGSI program includes DOE laboratory studies, international workshops, engagement with industry and the IAEA, and setting an example through its planned use in new nuclear facilities in the United States. Consistent with this effort, the NGSI program has sponsored 'Lessons Learned' studies and the preparation of facility-specific SBD Guidance documents. The NGSI program also takes into account successes that the NNSA has had with implementing safeguards early into facility designs within the U.S. The purpose of this paper is the presentation of the most recent developments in SBD under NGSI within the U.S. as well as the presentation of 'Lessons Learned' integrating safeguards into new nuclear facility designs of the U.S. Nuclear Security Enterprise (NSE), namely the Uranium Processing Facility (UPF) project at the Y-12 National Security Complex in Oak Ridge, Tennessee and to discuss its relevance to international safeguards. The paper is followed by the slides of the presentation. (author)

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)

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

“REDD+” is a mechanism created under the United Nations Framework Convention on Climate Change (UNFCCC) for Reducing {carbon} Emissions from Deforestation and Degradation and forest enhancement. In addition, REDD+ “safeguards” are intended to protect non-carbon forest values. While REDD+ countries are formally requested to provide information on safeguards, there is as yet no agreement on the relative priority of carbon versus non-carbon values, and the appropriate level of safeguard standardization. This, we argue, has allowed REDD+ to function as a “boundary object” spanning disparate priorities. Meanwhile, the contestation of these priorities has been displaced from intergovernmental processes to the various organizations involved in operationalizing REDD+ activities. This article applies a set of organizational, substantive and conceptual typologies to compare differences in the balance of actors, interests and ideas across these organizations. It finds that multi-lateral funding programs have drawn heavily on existing safeguards for international aid, while private certification schemes have specialized in different niche priorities at the project level. In regards to the substance of safeguard requirements, the involvement of donors and investors appears correlated with a stronger emphasis on carbon and risk mitigation while greater NGO involvement and the decoupling of safeguards design from REDD+ funding appear correlated with greater emphasis on social rights and benefits. These findings have several critical implications for future REDD+ activities. Firstly, the choice of organizations involved in defining, funding and verifying safeguard activities, and the balance of actors in their governing structures, are likely to influence the relative emphasis on non-carbon values. Secondly, a diversity of approaches to disbursing REDD+ incentives may be necessary to maintain widespread support for REDD+. Thirdly, it remains to be seen whether REDD

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

IAEA safeguards and the additional protocol in the Eurasia Region

International Nuclear Information System (INIS)

Murakami, K.

2001-01-01

Developing and implementing safeguards against misuse of nuclear material and facilities has always been the Agency's main activities. Like the nuclear non-proliferation regime itself, the development of the safeguards system has been an evolutionary process. The first safeguards inspection was carried out in 1962 (in Norway). In the sixties, the basic concepts behind safeguards were developed (INFCIRC/26, adopted in 1961, for some of you it might still have a familiar ring) and the number of inspections and types of facilities inspected grew slowly. With the advent of INFCIRC/66/Rev. 2, a more complete, albeit limited, system of safeguards covering nuclear material, equipment and facilities emerged. But the quantum leap came, of course, wit the entry into force of the NPT. Today, the IAEA has 224 safeguards agreements in force with 140 States. Nearly all of these States are NPT States. In the Eurasia Region, particularly the Newly Independent States (NIS) significant achievements have been made in the Safeguards Implementation. States with nuclear activities have the SG Agreement in force. Some states are already signing the Additional Protocol and it is in force in two of these States in the NIS region. Much progress has been made in the area of nuclear material and accountancy through the IAEA Coordinated Technical Support Programme (CTSP). The programme was organized to co-ordinate the donor states activities and has been successful for the last seven years in providing assistance in the area of nuclear legislation establishment of the State System of Accountancy of nuclear material (SSAC) and other related areas. Improvement is still foreseen in these areas, particularly as more states in the region will be signing and implementing the Additional Protocols

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

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)

IAEA Guidance for Safeguards Implementation in Facility Design and Construction

International Nuclear Information System (INIS)

Sprinkle, J.; Hamilton, A.; Poirier, S.; Catton, A.; Ciuculescu, C.; Ingegneri, M.; Plenteda, R.

2015-01-01

), · International Safeguards in the Design of Conversion Plants (NF-T-4.8, tbd), · International Safeguards in the Design of Enrichment Plants (NF-T-4.9, tbd), · International Safeguards in the Design of Reprocessing Plants (NF-T-3.2, tbd), The presentation will address how these publications can be shared and promoted. It will include lessons learned and suggestions how to affect the new facility bidding process in a constructive way. (author)

Terminating Safeguards on Excess Special Nuclear Material: Defense TRU Waste Clean-up and Nonproliferation - 12426

Energy Technology Data Exchange (ETDEWEB)

Hayes, Timothy [Los Alamos National Laboratory, Carlsbad Operations Group (United States); Nelson, Roger [Department Of Energy, Carlsbad Operations Office (United States)

2012-07-01

The Department of Energy (DOE) and the National Nuclear Security Administration (NNSA) manages defense nuclear material that has been determined to be excess to programmatic needs and declared waste. When these wastes contain plutonium, they almost always meet the definition of defense transuranic (TRU) waste and are thus eligible for disposal at the Waste Isolation Pilot Plant (WIPP). The DOE operates the WIPP in a manner that physical protections for attractiveness level D or higher special nuclear material (SNM) are not the normal operating condition. Therefore, there is currently a requirement to terminate safeguards before disposal of these wastes at the WIPP. Presented are the processes used to terminate safeguards, lessons learned during the termination process, and how these approaches might be useful for future defense TRU waste needing safeguards termination prior to shipment and disposal at the WIPP. Also described is a new criticality control container, which will increase the amount of fissile material that can be loaded per container, and how it will save significant taxpayer dollars. Retrieval, compliant packaging and shipment of retrievably stored legacy TRU waste has dominated disposal operations at WIPP since it began operations 12 years ago. But because most of this legacy waste has successfully been emplaced in WIPP, the TRU waste clean-up focus is turning to newly-generated TRU materials. A major component will be transuranic SNM, currently managed in safeguards-protected vaults around the weapons complex. As DOE and NNSA continue to consolidate and shrink the weapons complex footprint, it is expected that significant quantities of transuranic SNM will be declared surplus to the nation's needs. Safeguards termination of SNM varies due to the wide range of attractiveness level of the potential material that may be directly discarded as waste. To enhance the efficiency of shipping waste with high TRU fissile content to WIPP, DOE designed an

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'

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

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

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

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

Tracking and position recognition applied to remote monitoring to be used in integrated safeguards

Energy Technology Data Exchange (ETDEWEB)

Bonino, Anibal D; Perez, Adrian C; Krimer, Mario J; Teira, Ruben O; Vigile, Rodolfo S; Valentino, Lucia I; Giordano, Luis A; Ferro, Juan M [Autoridad Regulatoria Nuclear, Buenos Aires (Argentina)

2001-07-01

In the framework of the Strengthening and integrated Safeguards Systems new measures and tools are available to meet the safeguards objective. The credible assurance on the absence of undeclared nuclear material and activities derived from the implementation of the Additional Protocol has an impact on the current safeguards approach to declared facilities thus their through review is advisable. Among these tools, a more intensive use of unattended systems and remote transmission of safeguards relevant information are considered, specifically for On Load Reactors (ORLs). A Remote Monitoring Systems (RMS) to cover the transfers of spent fuels from the ponds to a dry storage is being tested at Embalse nuclear power plant. In connection with the RMS, this paper describes some of the technologies involved: the Global Position System (GPS) and the Radio Frequency IDentification (RFID), which were implemented due to the requirement to ascertain the position of valuable elements. The main objective of this design aimed at safeguarding the spent fuels transfers from the welding cell to the silos field by a strict surveillance of the whereabouts. The bases for the development were settled by the specifications imposed by the integrated Safeguards of the Nuclear Regulatory Authority in Argentina. The resultant tracking and position recognition system is based on GPS receivers operating in Differential Mode, with the aid of Radio Frequency Identification. In compliance with the safeguard requirement the whole system is able to operate in a continuous and remote mode, what means without human being attention. (author)

Technical criteria for terminating or reducing domestic safeguards on low-grade special nuclear material

International Nuclear Information System (INIS)

Crawford, D.W.

1996-01-01

A graded table for terminating or reducing domestic safeguards has been developed for use by programs and facilities within the Department of Energy in decisions regarding the need for or levels of protection of low-grade nuclear materials. Contained in this table are technical criteria which can allow for complete removal of safeguards over many special nuclear material forms and concentrations of typical low-grade materials either currently located at generating or processing sites and materials which may arise from processing operations related to stabilization and disposition activities. In addition, these criteria include higher concentration levels which may warrant maintaining some level of (albeit reduced) security on low-grade materials while allowing reductions in materials control and accountability requirements. These reductions can range from complete removal of these materials from materials control and accountability requirements such as measurements, physical inventories and recordkeeping, to deferring these measurements and physical inventories until a time that either the material is removed from the site or resubmitted for processing. It is important to note that other conditions contained in current Departmental safeguards and security policy be met prior to safeguards termination or reduction

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

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...

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

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

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...

Safeguardability assessment on pilot-scale advanced spent fuel conditioning facility

International Nuclear Information System (INIS)

Lee, S.Y.; Li, T.K.; Pickett, S.E.; Miller, M.C.; Ko, W.I.; Kim, H.D.

2006-01-01

Full text: In South Korea, approximately 6,000 metric tons of spent nuclear fuel from commercial reactor operation has been accumulated with the expectation of more than 30,000 metric tons, three times the present storage capacity, by the end of 2040. To resolve these challenges in spent fuel management, the Korea Atomic Energy Research Institute (KAERI) has been developing a dry reprocessing technology called Advanced Spent Fuel Conditioning Process (ACP). This is an electrometallurgical treatment technique to convert oxide-type spent fuel into a metallic form, and the electrolytic reduction (ER) technology developed recently is known as a more efficient concept for spent fuel conditioning. The goal of the ACP study is to recover more than 99% of the actinide elements into a metallic form with minimizing the volume and heat load of spent fuel. The significant reduction of the volume and heat load of spent fuel is expected to lighten the burden of final disposal in terms of disposal size, safety, and economics. In the framework of R and D collaboration for the ACP safeguards, a joint study on the safeguardability of the ACP technology has been performed by the Los Alamos National Laboratory (LANL) and KAERI. The purpose of this study is to address the safeguardability of the ACP technology, through analysis of material flow and development of a proper safeguards system that meet IAEA's comprehensive safeguards objective. The sub-processes and material flow of the pilot-scale ACP facility were analyzed, and subsequently the relevant material balance area (MBA) and key measurement point (KMP) were designed for material accounting. The uncertainties in material accounting were also estimated with international target values, and design requirements for the material accounting systems were derived

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

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)

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)

Concerns when designing a safeguards approach for the back-end of the Swedish nuclear fuel cycle

Energy Technology Data Exchange (ETDEWEB)

Fritzell, Anni (Uppsala Univ., Uppsala (Sweden))

2008-03-15

In Sweden, the construction of an encapsulation plant and a geological repository for the final disposal of spent nuclear fuel is planned to start within the next ten years. Due to Sweden's international agreements on non-proliferation, the Swedish safeguards regime must be extended to include these facilities. The geological repository has some unique features, which present the safeguards system with unprecedented challenges. These features include, inter alia, the long period of time that the facility will contain nuclear material and that the disposed nuclear material will be very difficult to access, implying that physical verification of its presence in the repository is not foreseen. This work presents the available techniques for creating a safeguards system for the backend of the Swedish nuclear fuel cycle. Important issues to consider in the planning and implementation of the safeguards system have been investigated, which in some cases has led to an identification of areas needing further research. The results include three proposed options for a safeguards approach, which have been evaluated on the basis of the safeguards authorities' requirements. Also, the evolution and present situation of the work carried out in connection to safeguards for geological repositories has been compiled

Maintaining continuity of knowledge on safeguards samples

International Nuclear Information System (INIS)

Franssen, F.; Islam, A.B.M.N.; Sonnier, C.; Schoeneman, J.L.; Baumann, M.

1992-01-01

The conclusions of the vulnerability test on VOPAN (verification of Operator's Analysis) as conducted at Safeguards Analytical Laboratory (ASA) at Seibersdorf, Austria in October 1990 and documented in STR-266, indicate that ''whenever samples are taken for safeguards purposes extreme care must be taken to ensure that they have not been interfered with during the sample taking, transportation, storage or sample preparation process.'' Indeed there exist a number of possibilities to alter the content of a safeguards sample vial from the moment of sampling up to the arrival of the treated (or untreated) sample at SAL. The time lapse between these two events can range from a few days up to months. The sample history over this period can be subdivided into three main sub-periods: (1) the period from when the sampling activities are commenced up to the treatment in the operator's laboratory, (2) during treatment of samples in the operator's laboratory, and finally, (3) the period between that treatment and the arrival of the sample at SAL. A combined effort between the Agency and the United States Support Program to the Agency (POTAS) has resulted in two active tasks and one proposed task to investigate improving the maintenance of continuity of knowledge on safeguards samples during the entire period of their existence. This paper describes the use of the Sample Vial Secure Container (SVSC), of the Authenticated Secure Container System (ASCS), and of the Secure Container for Storage and Transportation of samples (SCST) to guarantee that a representative portion of the solution sample will be received at SAL

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.

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

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'.

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

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.

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.

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

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

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.

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

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)