Safeguards Summary Event List (SSEL). Pre-NRC-June 30, 1985. Revision 11

International Nuclear Information System (INIS)

1986-01-01

The Safeguards Summary Event List (SSRL) provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission (NRC). Events are described under the categories of bomb-related, intrusion, missing and/or allegedly stolen, transportation, tampering/vandalism, arson, firearms, radiological sabotage, non-radiological sabotage and miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels. 12 figs

Safeguards Summary Event List (SSEL), Pre-NRC through December 31, 1983. Rev. 9

International Nuclear Information System (INIS)

1984-06-01

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

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.

Safeguards Summary Event List (SSEL). Pre-NRC through December 31, 1984. Revision 10

International Nuclear Information System (INIS)

1985-05-01

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

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

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 Summary Event List (SSEL), pre-NRC through December 31, 1982

International Nuclear Information System (INIS)

1983-08-01

This document represents a revision of the list published December 1980 of safeguards-related events involving NRC licensees and licensed material. It summarizes events occurring between June 30, 1982 and December 31, 1982. Editorial changes to earlier pages are also included

A safeguards program for implementing Department of Energy requirements

International Nuclear Information System (INIS)

Erkkila, B.H.

1989-01-01

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

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

Nuclear Safeguards Infrastructure Required for the Next Generation Nuclear Plant (NGNP)

Energy Technology Data Exchange (ETDEWEB)

Dr. Mark Schanfein; Philip Casey Durst

2012-07-01

The Next Generation Nuclear Plant (NGNP) is a Very High Temperature Gas-Cooled Reactor (VHTR) to be constructed near Idaho Falls, Idaho The NGNP is intrinsically safer than current reactors and is planned for startup ca. 2021 Safety is more prominent in the minds of the Public and Governing Officials following the nuclear reactor meltdown accidents in Fukushima, Japan The authors propose that the NGNP should be designed with International (IAEA) Safeguards in mind to support export to Non-Nuclear-Weapons States There are two variants of the NGNP design; one using integral Prismatic-shaped fuel assemblies in a fixed core; and one using recirculating fuel balls (or Pebbles) The following presents the infrastructure required to safeguard the NGNP This infrastructure is required to safeguard the Prismatic and Pebble-fueled NGNP (and other HTGR/VHTR) The infrastructure is based on current Safeguards Requirements and Practices implemented by the International Atomic Energy Agency (IAEA) for similar reactors The authors of this presentation have worked for decades in the area of International Nuclear Safeguards and are recognized experts in this field Presentation for INMM conference in July 2012.

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

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

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)

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)

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

Oak Ridge National Laboratory Next-Generation Safeguards Initiative: Human Capital Development

Energy Technology Data Exchange (ETDEWEB)

Gilligan, Kimberly [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2014-01-01

In 2007, the US Department of Energy National Nuclear Security Administration (DOE/NNSA) Office of Nonproliferation and International Security (NA-24) completed a comprehensive review of the current and potential future challenges facing the international safeguards system. The review examined: trends and events that have an effect on the mission of international safeguards; the implications of expanding and evolving mission requirements of the legal authorities and institutions that serve as the foundation of the international safeguards system; and, the technological, financial, and human resources required for effective safeguards implementation. The review’s findings and recommendations were summarized in the report International Safeguards: Challenges and Opportunities for the 21st Century (October 2007). The executive summary is available at the following link: http://nnsa.energy.gov/sites/default/files/nnsa/inlinefiles/NGSI_Report.pdf.

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

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

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

The urgent requirement for new radioanalytical certified reference materials for nuclear safeguards, forensics, and consequence management

International Nuclear Information System (INIS)

Inn, K.G.W.; Martin Johnson, Jr.C.; Warren Oldham; Lav Tandon; Simon Jerome; Thomas Schaaff; Robert Jones; Daniel Mackney; Pam MacKill; Brett Palmer

2013-01-01

A multi-agency workshop was held from 25 to 27 August 2009, at the National Institute of Standards and Technology (NIST), to identify and prioritize the development of radioanalytical Certified Reference Materials (CRMs, generally provided by National Metrology Institutes; Standard Reference Materials, a CRM issued by NIST) for field and laboratory nuclear measurement methods to be used to assess the consequences of a domestic or international nuclear event. Without these CRMs, policy makers concerned with detecting proliferation and trafficking of nuclear materials, attribution and retribution following a nuclear event, and public health consequences of a nuclear event would have difficulty making decisions based on analytical data that would stand up to scientific, public, and judicial scrutiny. The workshop concentrated on three areas: post-incident Improvised Nuclear Device (IND) nuclear forensics, safeguard materials characterization, and consequence management for an IND or a Radiological Dispersion Device detonation scenario. The workshop identified specific CRM requirements to fulfill the needs for these three measurement communities. Of highest priority are: (1) isotope dilution mass spectrometry standards, specifically 233 U, 236 gNp, 244 Pu, and 243 Am, used for quantitative analysis of the respective elements that are in critically short supply and in urgent need of replenishment and certification; (2) CRMs that are urgently needed for post-detonation debris analysis of actinides and fission fragments, and (3) CRMs used for destructive and nondestructive analyses for safeguards measurements, and radioisotopes of interest in environmental matrices. (author)

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

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

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

Video image processing for nuclear safeguards

International Nuclear Information System (INIS)

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

1995-01-01

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

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)

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)

Oak Ridge National Laboratory Next Generation Safeguards Initiative

Energy Technology Data Exchange (ETDEWEB)

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

2011-12-01

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

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.

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

Assessment of the requirements for placing and maintaining Savannah River Site spent fuel storage basins under International Atomic Energy Agency safeguards

International Nuclear Information System (INIS)

Amacker, O.P. Jr.; Curtis, M.M.; Delegard, C.H.; Hsue, S.T.; Whitesel, R.N.

1997-03-01

The United States is considering the offer of irradiated research reactor spent fuel (RRSF) for international safeguards applied by the International Atomic Energy Agency (IAEA). The offer would be to add one or more spent fuel storage basins to the list of facilities eligible for IAEA safeguards. The fuel to be safeguarded would be stored in basins on the Savannah River Site (SRS). This RRSF potentially can include returns of Material Test Reactor (MTR) VAX fuel from Argentina, Brazil, and Chile (ABC); returns from other foreign research reactors; and fuel from domestic research reactors. Basins on the SRS being considered for this fuel storage are the Receiving Basin for Offsite Fuel (RBOF) and the L-Area Disassembly Basin (L-Basin). A working group of SRS, U.S. Department of Energy International Safeguards Division (NN-44), and National Laboratory personnel with experience in IAEA safeguards was convened to consider the requirements for applying the safeguards to this material. The working group projected the safeguards requirements and described alternatives

Challenges for Incorporation of additional safeguards requirements in a fuel fabrication facility in Japan

International Nuclear Information System (INIS)

Ishikawa, Tadatsugu; Suzuki, Katsuyuki

2004-01-01

Recent introduction of strengthened SG measure (i.e.: SNRI (Short Notice Random Inspection)) necessitated semi-real-time reporting including non-prescribed data in the FA for vital processes. These requirements have been bet by endeavors of both Inspectorates and operators. Using the integrated databases it will also be possible to produce most of reports required for safeguards purposes on a semi-real time basis, albeit with additional investment for softwares. However, in order to fully enjoy the advancements of information technology it is necessary to streamline the legal and procedural platform in addition to technical matters, in particular what are 'must' for safeguards and abolish if they are not really needed anymore. (author)

Design impacts of safeguards and security requirements for a US MOX fuel fabrication facility

International Nuclear Information System (INIS)

Erkkila, B.H.; Rinard, P.M.; Thomas, K.E.; Zack, N.R.; Jaeger, C.D.

1998-01-01

The disposition of plutonium that is no longer required for the nation's defense is being structured to mitigate risks associated with the material's availability. In the 1997 Record of Decision, the US Government endorsed a dual-track approach that could employ domestic commercial reactors to effect the disposition of a portion of the plutonium in the form of mixed oxide (MOX) reactor fuels. To support this decision, the Office of Materials Disposition requested preparation of a document that would review US requirements for safeguards and security and describe their impact on the design of a MOX fuel fabrication facility. The intended users are potential bidders for the construction and operation of the facility. The document emphasizes the relevant DOE Orders but also considers the Nuclear Regulatory Commission (NRC) requirements. Where they are significantly different, the authors have highlighted this difference and provided guidance on the impact to the facility design. Finally, the impacts of International Atomic Energy Agency (IAEA) safeguards on facility design are discussed. Security and materials control and accountability issues that influence facility design are emphasized in each area of discussion. This paper will discuss the prepared report and the issues associated with facility design for implementing practical, modern safeguards and security systems into a new MOX fuel fabrication facility

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)

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

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

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 - 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 planning in a plant design process

International Nuclear Information System (INIS)

Heinrich, L.A.

1977-01-01

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

47 CFR 64.2009 - Safeguards required for use of customer proprietary network information.

Science.gov (United States)

2010-10-01

... other manner, of their own and their affiliates' sales and marketing campaigns that use their customers... outbound marketing request for customer approval. (e) A telecommunications carrier must have an officer, as... 47 Telecommunication 3 2010-10-01 2010-10-01 false Safeguards required for use of customer...

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

Non-proliferation of nuclear weapons and nuclear security. Overview of safeguards requirements for States with limited nuclear material and activities

International Nuclear Information System (INIS)

Lodding, J.; Ribeiro, B.

2006-06-01

This booklet provides an overview of safeguards obligations that apply to States which are parties to the Nuclear Non-Proliferation Treaty (NPT) that have no nuclear facilities and only limited quantities of nuclear material. Most State parties to the NPT have no nuclear facilities and only limited quantities of nuclear material. For such States, safeguards implementation is expected to be simple and straightforward. This booklet provides an overview of the safeguards obligations that apply to such States. It is hoped that a better understanding of these requirements will facilitate the conclusion and implementation of safeguards agreements and additional protocols, and thereby contribute to the strengthening of the IAEA?s safeguards system and of collective security

Non-proliferation of nuclear weapons and nuclear security. Overview of Safeguards requirements for States with limited nuclear material and activities

International Nuclear Information System (INIS)

Lodding, J.; Ribeiro, B.

2006-06-01

This booklet provides an overview of safeguards obligations that apply to States which are parties to the Nuclear Non-Proliferation Treaty (NPT) that have no nuclear facilities and only limited quantities of nuclear material. Most State parties to the NPT have no nuclear facilities and only limited quantities of nuclear material. For such States, safeguards implementation is expected to be simple and straightforward. This booklet provides an overview of the safeguards obligations that apply to such States. It is hoped that a better understanding of these requirements will facilitate the conclusion and implementation of safeguards agreements and additional protocols, and thereby contribute to the strengthening of the IAEA?s safeguards system and of collective security

Societal risk approach to safeguards design and evaluation

International Nuclear Information System (INIS)

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

1975-01-01

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

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

IAEA safeguards for the Fissile Materials Disposition Project

International Nuclear Information System (INIS)

Close, D.A.

1995-06-01

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

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

The Concept of Goals-Driven Safeguards

International Nuclear Information System (INIS)

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

2009-01-01

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

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)

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.

Application of Safeguards-by-Design to a Reactor Design Process

International Nuclear Information System (INIS)

Whitlock, J.J.

2010-01-01

The application of 'Safeguards-by-Design' (SBD) to a reactor design process is described. The SBD concept seeks to improve the efficiency and effectiveness of IAEA safeguards by incorporating the needs of safeguards at an early stage of reactor design. Understanding and accommodating safeguards in the design process requires a set of 'design requirements for safeguards'; however, such requirements (a) do not traditionally exist, and (b) must exist alongside other more traditional design requirements based upon compliance and operational goals. In the absence of design requirements, a 'Design Guide' for safeguards was created, consisting of recommendations based on best practices. To acquire an understanding of safeguards requirements at the design level, a systematic accounting of diversion pathways was required. However, because of the crowded field of other design requirements, this process needed a methodology that was also flexible in interpretation. The GenIV Proliferation Resistance and Physical Protection (PR and PP) methodology (Rev.5, 2005) was chosen for this exercise. The PR and PP methodology is a general approach and therefore it was necessary to restrict its application; in effect, turning 'off' various options so as to simplify the process. The results of this exercise were used to stimulate discussions with the design team and initiate changes that accommodate safeguards without negatively impacting other design requirements. The process yielded insights into the effective application of SBD, and highlighted issues that must be resolved for effective incorporation of an 'SBD culture' within the design process. (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

{sup 3}He Replacement for Nuclear Safeguards Applications- an integrated test program to compare alternative neutron detectors

Energy Technology Data Exchange (ETDEWEB)

Menlove, H. O.; Henzlova, D.; Evans, L. G.; Swinhoe, M. T.; Marlow, J. B. [Los Alamos National Laboratory, Safeguards Science and Technology Group, Los Alamos, (United States)

2011-12-15

During the past several years, the demand for {sup 3}He gas has far exceeded the gas supply. This shortage of {sup 3}He gas is projected to continue into the foreseeable future. There is a need for alternative neutron detectors that do not require {sup 3}He gas. For more than four decades, neutron detection has played a fundamental role in the safeguarding and control of nuclear materials at production facilities, fabrication plants and storage sites worldwide. Neutron measurements for safeguards applications have requirements that are unique to the quantitative assay of special nuclear materials. These neutron systems measure the neutron multiplicity distributions from each spontaneous fission and/or induced fission event. The neutron time correlation counting requires that two or more neutrons from a single fission event be detected. The doubles and triples neutron counting rate depends on the detector efficiency to the 2nd and 3rd power, respectively, so low efficiency systems will not work for the coincidence measurements, and any detector instabilities are greatly amplified. In the current test program, we will measure the alternative detector properties including efficiency, die-away time, multiplicity precision, gamma sensitivity, dead-time, and we will also consider the detector properties that would allow commercial production to safeguards scale assay systems. This last step needs to be accomplished before the proposed technologies can reduce the demand on {sup 3}He gas in the safeguards world. This paper will present the methodology that includes MCNPX simulations for comparing divergent detector types such as {sup 10}B lined proportional counters with {sup 3}He gas based systems where the performance metrics focus on safeguards applications.

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.)

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 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)

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

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

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

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...

Safeguards summary event list (SSEL)

International Nuclear Information System (INIS)

Davidson, J.J.; MacMurdy, P.H.

1980-12-01

The List contains nine categories of events involving NRC licensed material or licensees. It is deliberately broad in scope for two main reasons. First, the list is designed to serve as a reference document. It is as complete and accurate as possible. Second, the list is intended to provide as broad a perspective of the nature of licensee-related events as possible. The nine categories of events are as follows: bomb-related events; intrusion events; missing and/or allegedly stolen events; transportation-related events; vandalism events; arson events; firearms-related events; sabotage events; and miscellaneous events

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)

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)

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).

The development of safeguards for geological repositories

International Nuclear Information System (INIS)

Van der Meer, K.

2009-01-01

Traditionally, research and development on geological repositories for High Level Waste (HLW) focuses on the short- and long-term safety aspects of the repository. If the repository will also be used for the disposal of spent fuel, safeguards aspects have to be taken into account. Safety and safeguards requirements may be contradictory; the safety of a geological repository is based on the non-intrusion of the geological containment, while safeguards require regular inspections of position and amount of the spent fuel. Examples to reconcile these contradictory requirements are the use of information required for the safety assessment of the geological repository for safeguards purposes and the adaptation of the safeguards approach to use non-intrusive inspection techniques. The principles of an inspection approach for a geological repository are now generally accepted within the IAEA. The practical applicability of the envisaged inspection techniques is still subject to investigation. It is specifically important for the Belgian situation that an inspection technique can be used in clay, the geological medium in which Belgium intends to dispose its HLW and spent fuel. The work reported in this chapter is the result of an international cooperation in the framework of the IAEA, in which SCK-CEN participates

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 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

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 status of United States R and D programs in safeguards and physical protection

International Nuclear Information System (INIS)

Mangan, D.L.; Tape, J.W.

1993-01-01

The breakup of former Soviet Union and the strategic nuclear arms reduction agreements, START 1 and 2, when fully implemented, will result in the significant reduction and dismantlement of nuclear weapons. These events will produce the significant increase of stored nuclear materials requiring the utmost control and care for indefinite future. Some of these materials in addition to existing wastes and residues may need further processing. The control of nuclear materials through safeguards, both domestic and international, is one of only a few effective barriers to nuclear proliferation. The improved technology is the key to the cost effective safeguards of nuclear materials. The Department of Energy carries out the research and development programs at its national laboratories. As the most notable demonstration and training efforts of new technologies, there is International Training Courses on the State System of Accounting and Control and the Physical Protection of Nuclear Facilities and Materials. The Office of Research and Development of the Office of Intelligence and National Security Affairs, the Department of Energy, the Office of Safeguards and Security, International Safeguards Division and so on carry out the activities of the R and D on safeguards and physical protection. (K.I.)

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

Nuclear Security and Nuclear Safeguards; Differences, Commonalities and Synergies

International Nuclear Information System (INIS)

Jorant, C.

2015-01-01

Reference to the three S's in the nuclear world is recurring and much has been said about the need to build on synergies to reinforce safeguards, safety and security. In practice, the 3S's communities are seldom interconnected even though some interaction can be observed between safety and security and security and safeguards. Ensuring a better understanding between those three sectors about their scope, requirements, implementation methods and tools would stimulate cooperation. The second Nuclear Security Summit and particularly the industry related event stressed the synergies between safety and security. The first IAEAs Security Conference organized in July 2013 did not address specifically nuclear safeguards and security relations. Last Security Summit took place in The Hague in March 2014 and this type of issue was not really raised either. The safeguards Symposium provides a timely opportunity to tackle possible enhanced cooperation between safeguards and security communities and assess the prospect for addressing such issue at the next and allegedly last security summit in 2016. This presentation will analyze the differences and commonalities between those two sectors, in particular with regards to the objectives and actors, the organization and technicalities, or to the conceptual approaches (DBT and APA/SLC, attractiveness/accessibility). It will then assess the possible synergies or cooperation between both communities. It will discuss the merits of a global and comprehensive involvement of the different actors, (State, industry and international bodies including the NGOs) and of exchanges on good practices to contribute to a common understanding and references while allowing for an adaptable and national approach. Indeed the need to reassure the stakeholders, including the general public, that security, as well as safeguards are addressed in a consistent manner worldwide is of utmost importance for building future nuclear energy programmes on a

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

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

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

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

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

Norm in the matter of safeguards

International Nuclear Information System (INIS)

Saavedra, Analia; Maceiras, Elena; Valentino, Lucia; Chiliutti, Mauro

2001-01-01

The Nuclear Regulatory Authority (NRA), through its norm, establishes requirements in the matter of safeguards that allow him to control the fulfillment of the objectives established at national level and the international commitments that the Argentine Republic has assumed in the scope of Nuclear Non-proliferation. The measures of fortification of the safeguards proposed by the International Atomic Energy Agency (IAEA), will imply new obligations for the country and consequently it will require the update of the effective norm in the matter. The objective of this work is to describe the reach of the update of the norm in the matter of safeguards and their relation with some procedures of application in the scope of the radiological protection and the nuclear security

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

International safeguards problem

International Nuclear Information System (INIS)

Scheinman, L.; Curtis, H.B.

1977-01-01

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

Implementing Safeguards-by-Design

International Nuclear Information System (INIS)

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

2010-01-01

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

An integrated approach to validation of safeguards and security program performance

International Nuclear Information System (INIS)

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

1988-01-01

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

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

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

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 information system

International Nuclear Information System (INIS)

Nardi, J.

1984-01-01

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

Some reflections on nuclear safeguards

International Nuclear Information System (INIS)

Campbell, Ross.

1981-01-01

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

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

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

Elementary survey of nuclear safeguards problems

International Nuclear Information System (INIS)

Tobias, M.L.

1975-01-01

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

Principles in safeguards: A Canadian perspective

International Nuclear Information System (INIS)

Keen, L.J.

2007-01-01

L.J. Keen presented the Canadian perspective on safeguards. She noted that the IAEA safeguards system has responded well to challenges and has acted as the effective early warning system that it was intended to be. The exit from the non-proliferation regime by the Democratic People's Republic of Korea has demonstrated how effective safeguards and verification are seen to be in detecting proliferation activity. The main areas of importance for Canada are effectiveness, efficiency and transparency. Effectiveness requires information and access, and assures citizens of the exclusively peaceful uses of nuclear energy. Efficiency requires risk informed decisions for the sound allocation of resources and the early incorporation of proliferation resistance in design and construction, so that IAEA efforts can concentrate on where the risks are greatest. Openness and transparency include the public, and for the IAEA this includes its Member States since ultimately they control its activities and finances. Canada received its broader safeguards conclusion in 2005 and intends to maintain it. This will require continuous improvement in an era of rapid expansion of the nuclear industry. One problem foreseen is the adequate supply of qualified personnel, with the CNSC's resources growing at about 12%. The CNSC is looking at internal training programmes and internships

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

Development of safeguards information treatment system at the facility level

Energy Technology Data Exchange (ETDEWEB)

Lee, Byung Doo; Song, Dae Yong; So, Dong Sup; Kwack, Eun Ho [Korea Atomic Energy Research Institute, Taejeon (Korea)

2000-04-01

Safeguards Information Treatment System(SITS) at the facility level is required to implement efficiently the obligations under the Korea-IAEA Safeguards Agreement, bilateral agreements with other countries and domestic law. In this report, the requirements and major functions of SITS were considered, and the error checking methods and the relationships of safeguards information were reviewed. SITS will be developed to cover the different accounting procedures and methods applied at the various facilities under IAEA safeguards. Also, the resolved result of the Y2K problem in the existing nuclear material accounting program was described. 3 tabs. (Author)

Design and evaluation of an integrated safeguards system: principles

International Nuclear Information System (INIS)

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

1984-01-01

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

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

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.

Design and evaluation of an integrated safeguards system: principles

International Nuclear Information System (INIS)

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

1984-07-01

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

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)

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)

Domestic safeguards: annual report to Congress, fiscal year 1978

International Nuclear Information System (INIS)

1979-01-01

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

IAEA safeguards and detection of undeclared nuclear activities

Energy Technology Data Exchange (ETDEWEB)

Harry, R.J.S.

1996-03-01

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

IAEA safeguards and detection of undeclared nuclear activities

International Nuclear Information System (INIS)

Harry, R.J.S.

1996-03-01

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

Safeguards for geological repositories

International Nuclear Information System (INIS)

Fattah, A.

2000-01-01

substantially large. Change in social, economic, environmental and other scenarios might demand recovery of nuclear and other material from the repository sometime in the future. To this end, the Department of Safeguards has developed a policy paper to guide the planner, designer and operator to incorporate safeguards related features, as appropriate. In parallel, a programme for the Development of Safeguards for Final Disposal of Spent Fuel in Geological Repositories (SAGOR) was launched to foster technological advancement. The mission of SAGOR has been to ensure that the safeguards systems developed for the final disposal of spent fuel effectively meet the objectives of IAEA safeguards, optimise IAEA resources, and make best use of existing technologies while still meeting the requirements for safety and environmental protection. (author)

Applying new safeguards technology to existing nuclear facilities

International Nuclear Information System (INIS)

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

1979-01-01

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

Applying new safeguards technology to existing nuclear facilities

International Nuclear Information System (INIS)

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

1979-01-01

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

ATLAS TDAQ/DCS Event Filter Event Handler Requirements

CERN Document Server

Bee, C P; Meessen, C; Qian, Z; Touchard, F; Green, P; Pinfold, J L; Wheeler, S; Negri, A; Scannicchio, D A; Vercesi, V

2002-01-01

The second iteration of the Software Development Process of the ATLAS Event Filter has been launched. A summary of the design phase of the first iteration is given in the introduction. The document gives constraints, use cases, functional and non-functional requirements for the Event Handler sub-system of the Event Filter.

Development of nuclear materials accounting for international safeguards

International Nuclear Information System (INIS)

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

1991-01-01

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

Training to raise staff awareness about safeguarding children.

Science.gov (United States)

Fleming, Jane

2015-04-01

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

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

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

Safeguards and security design guidelines for conceptual monitored retrievable storage (MRS) facilities

International Nuclear Information System (INIS)

Byers, K.R.; Clark, R.G.; Harms, N.L.; Roberts, F.P.

1984-07-01

Existing safeguards/security regulations and licensing requirements that may be applicable to an MRS facility are not currently well-defined. Protection requirements consistent with the NRC-graded safeguards approach are identified, as a baseline safeguards system with a comparison of the impacts on safeguards and security of salient features of the different storage concepts. In addition, MRS facility design features and operational considerations are proposed that would enhance facility protection and provide additional assurance that protection systems and procedures would be effectively implemented. 3 figures

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

A Comparative Study on Safeguards Implementation under Bilateral Nuclear Cooperation Agreements and the IAEA Comprehensive Safeguards Agreement

Energy Technology Data Exchange (ETDEWEB)

Jeon, Jihye; Kim, Ki-Hyun; Lee, Young Wook [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

2016-10-15

A Nuclear Cooperation Agreement (NCA) requires several conditions, so-called obligations, on the items under the agreement such as: 1) peaceful use, 2) retransfer consent, 3) consent prior to reprocessing or enrichment and 4) safeguards and security. These obligations of the NCAs are imposed by the supplier country. The Comprehensive Safeguards Agreement (CSA) between the International Atomic Energy Agency (IAEA) and its member states require similar activities. However, there is a significant gap in nuclear material accountancy between safeguards implementation under the NCA and CSA. The difference of those two frameworks is compared herein, focusing on the unique features of the NCA safeguards and its implications are presented. In this study, the NCAs between the ROK and Canada, Australia and US were analyzed since each of them is one of the ROK’s major nuclear trading partners. The safeguards implementation under the NCA is usually specified in an Administrative Arrangement (AA) under the Agreement. The ROK has two AAs in force with Canada and Australia among 29 countries with NCA. Recently, the AA with Canada was revised in December 2015, with those concepts mentioned above. The AA with the US is currently under discussion. Cooperation in nuclear energy between two countries could be further enhanced through reliable implementation of the NCA undertakings. Taking into account the unique features of the NCA, we need to establish effective strategy for fulfilling the obligation under the Agreement.

Safeguards and security progress report, January-December 1984

Energy Technology Data Exchange (ETDEWEB)

Smith, D.B. (comp.)

1986-01-01

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

Safeguards and security progress report, January-December 1984

International Nuclear Information System (INIS)

Smith, D.B.

1986-01-01

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

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

The structure of nuclear safeguards systems

International Nuclear Information System (INIS)

Coulter, C.A.

1989-01-01

Safeguards systems for facilities that handle special nuclear material combine procedural, protective, and materials accounting elements to prevent and/or detect sabotage and diversion or theft of material. Because most of the discussion in this course is devoted to materials accounting topics only, this chapter provides a brief introduction to some of the procedural and protective elements of safeguards systems, placing the materials accounting system in its proper context. The chapter begins by reviewing certain pertinent DOE definitions and then surveys some protection requirements and technology - protective personnel, personnel identification systems, barriers, detectors, and communication systems. Considered next are the procedures of personnel selection and monitoring, definition and division of job functions, and operation. The chapter then describes the way the procedural, protective, and materials accounting elements can be combined, becoming a total safeguards system. Although such a system necessarily requires elements of procedure, protection, and materials accounting, only the materials accounting gives positive assurance that nuclear material is not diverted or stolen

Nuclear material data management and integration. A safeguard perspective

International Nuclear Information System (INIS)

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

1999-01-01

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

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-by-Design: Guidance for Independent Spent Fuel Dry Storage Installations (ISFSI)

Energy Technology Data Exchange (ETDEWEB)

Trond Bjornard; Philip C. Durst

2012-05-01

This document summarizes the requirements and best practices for implementing international nuclear safeguards at independent spent fuel storage installations (ISFSIs), also known as Away-from- Reactor (AFR) storage facilities. These installations may provide wet or dry storage of spent fuel, although the safeguards guidance herein focuses on dry storage facilities. In principle, the safeguards guidance applies to both wet and dry storage. The reason for focusing on dry independent spent fuel storage installations is that this is one of the fastest growing nuclear installations worldwide. Independent spent fuel storage installations are typically outside of the safeguards nuclear material balance area (MBA) of the reactor. They may be located on the reactor site, but are generally considered by the International Atomic Energy Agency (IAEA) and the State Regulator/SSAC to be a separate facility. The need for this guidance is becoming increasingly urgent as more and more nuclear power plants move their spent fuel from resident spent fuel ponds to independent spent fuel storage installations. The safeguards requirements and best practices described herein are also relevant to the design and construction of regional independent spent fuel storage installations that nuclear power plant operators are starting to consider in the absence of a national long-term geological spent fuel repository. The following document has been prepared in support of two of the three foundational pillars for implementing Safeguards-by-Design (SBD). These are: i) defining the relevant safeguards requirements, and ii) defining the best practices for meeting the requirements. This document was prepared with the design of the latest independent dry spent fuel storage installations in mind and was prepared specifically as an aid for designers of commercial nuclear facilities to help them understand the relevant international requirements that follow from a country’s safeguards agreement with

Australian Safeguards and Non-Proliferation Office, Annual Report 2001-2002

International Nuclear Information System (INIS)

2002-01-01

During the year Australian Safeguards and Non-Proliferation Office (ASNO) continued our substantial contribution to the development and strengthening of international verification regimes concerned with weapons of mass destruction (WMD). Domestically, ASNO conducted, or contributed to, review of WMD- related legislation and administration, amending permits to enhance security arrangements, and beginning development of supporting legislative changes. Another major area of work is the replacement research reactor project, where ASNO has been closely involved through safeguards and security aspects. This year has been dominated by the terrorist attacks of 11 September 2001 on the United States, and ongoing consequences. These events, and the concern that terrorists would use WMD if they were able to acquire them, have served to emphasise the importance of effective counter-proliferation and counter-terrorism measures to complement the non-proliferation regimes. They have also focused attention on the need to deal with non- compliance with WMD treaty commitments. The key achivements reported for the year under review include: 1. All treaty and statutory requirements met in respect of: nuclear material and nuclear items in Australia, Australian uranium exports (Australian Obligated Nuclear Material), chemicals covered by the CWC (Chemical Weapons Convention) and establishment of CTBT(Comprehensive Nuclear-Test-Ban Treaty) monitoring stations; 2. Effective contribution to strengthening non-proliferation verification regimes and counter terrorism initiatives: ongoing support for IAEA safeguards development, regional outreach on IAEA safeguards, CWC implementation and encouraging CTBT ratification, ANSTO security upgraded; security plan approved for construction of replacement research reactor, review, with other responsible authorities, of security of CWC related chemicals, and radiation sources

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

FEMO, A FLOW AND ENRICHMENT MONITOR FOR VERIFYING COMPLIANCE WITH INTERNATIONAL SAFEGUARDS REQUIREMENTS AT A GAS CENTRIFUGE ENRICHMENT FACILITY

International Nuclear Information System (INIS)

Gunning, John E.; Laughter, Mark D.; March-Leuba, Jose A.

2008-01-01

A number of countries have received construction licenses or are contemplating the construction of large-capacity gas centrifuge enrichment plants (GCEPs). The capability to independently verify nuclear material flows is a key component of international safeguards approaches, and the IAEA does not currently have an approved method to continuously monitor the mass flow of 235U in uranium hexafluoride (UF6) gas streams. Oak Ridge National Laboratory is investigating the development of a flow and enrichment monitor, or FEMO, based on an existing blend-down monitoring system (BDMS). The BDMS was designed to continuously monitor both 235U mass flow and enrichment of UF6 streams at the low pressures similar to those which exists at GCEPs. BDMSs have been installed at three sites-the first unit has operated successfully in an unattended environment for approximately 10 years. To be acceptable to GCEP operators, it is essential that the instrument be installed and maintained without interrupting operations. A means to continuously verify flow as is proposed by FEMO will likely be needed to monitor safeguards at large-capacity plants. This will enable the safeguards effectiveness that currently exists at smaller plants to be maintained at the larger facilities and also has the potential to reduce labor costs associated with inspections at current and future plants. This paper describes the FEMO design requirements, operating capabilities, and development work required before field demonstration.

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 - a system in transition

International Nuclear Information System (INIS)

Carlson, J.

1999-01-01

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

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

10 CFR 73.22 - Protection of Safeguards Information: Specific requirements.

Science.gov (United States)

2010-01-01

... protection. Information not classified as Restricted Data or National Security Information related to physical protection, including: (i) The composite physical security plan for the facility or site; (ii... Safeguards Information. (2) Each computer not located within an approved and lockable security storage...

CIPSS [computer-integrated process and safeguards system]: The integration of computer-integrated manufacturing and robotics with safeguards, security, and process operations

International Nuclear Information System (INIS)

Leonard, R.S.; Evans, J.C.

1987-01-01

This poster session describes the computer-integrated process and safeguards system (CIPSS). The CIPSS combines systems developed for factory automation and automated mechanical functions (robots) with varying degrees of intelligence (expert systems) to create an integrated system that would satisfy current and emerging security and safeguards requirements. Specifically, CIPSS is an extension of the automated physical security functions concepts. The CIPSS also incorporates the concepts of computer-integrated manufacturing (CIM) with integrated safeguards concepts, and draws upon the Defense Advance Research Project Agency's (DARPA's) strategic computing program

Panel on protection and management of plutonium: Subpanel on safeguards and security

International Nuclear Information System (INIS)

Tape, J.W.

1995-01-01

Nuclear materials safeguards and security systems are described in the context of the nuclear nonproliferation regime. Materials of interest to safeguards, threats, proposals to strengthen International Atomic Energy Agency safeguards, evolving safeguards issues and requirements, system effectiveness, and elements of a global nuclear materials management regime are discussed. Safeguards are seen as an essential element of nuclear materials management, but not a driver for decisions regarding nuclear power or the disposal of excess weapon nuclear materials

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

Investigation of novel spent fuel verification system for safeguard application

Energy Technology Data Exchange (ETDEWEB)

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

2016-10-15

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

Investigation of novel spent fuel verification system for safeguard application

International Nuclear Information System (INIS)

Lee, Haneol; Yim, Man-Sung

2016-01-01

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

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)

Process data in safeguards at the Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Ehinger, M.H.

1988-01-01

The desire to improve timeliness and sensitivity of material control and accounting capabilities is the basis for evaluation and upgrade of regulatory requirements throughout the nuclear industry. Improvements invariably require better measurement capabilities and more frequent measurements. Operating plants typically include a broad range of measurements and equipment devoted to process control. How can these measurements be used to benefit safeguards? A part of the Consolidated Fuel Reprocessing Program at the Oak Ridge National Laboratory has focused on the use of process data for safeguards. This report discusses recent safeguards demonstrations and current activities in a test facility at Oak Ridge

Termination of Safeguards for Accountable Nuclear Materials at the Idaho National Laboratory

International Nuclear Information System (INIS)

Holzemer, Michael; Carvo, Alan

2012-01-01

Termination of safeguards ends requirements of Nuclear Material Control and Accountability (MC and A) and thereby removes the safeguards basis for applying physical protection requirements for theft and diversion of nuclear material, providing termination requirements are met as described. Department of Energy (DOE) M 470.4 6 (Nuclear Material Control and Accountability [8/26/05]) stipulates: 1. Section A, Chapter I (1)( q) (1): Safeguards can be terminated on nuclear materials provided the following conditions are met: (a) 'If the material is special nuclear material (SNM) or protected as SNM, it must be attractiveness level E and have a measured value.' (b) 'The material has been determined by DOE line management to be of no programmatic value to DOE.' (c) 'The material is transferred to the control of a waste management organization where the material is accounted for and protected in accordance with waste management regulations. The material must not be collocated with other accountable nuclear materials.' Requirements for safeguards termination depend on the safeguards attractiveness levels of the material. For attractiveness level E, approval has been granted from the DOE Idaho Operations Office (DOE ID) to Battelle Energy Alliance, LLC (BEA) Safeguards and Security (S and S). In some cases, it may be necessary to dispose of nuclear materials of attractiveness level D or higher. Termination of safeguards for such materials must be approved by the Departmental Element (this is the DOE Headquarters Office of Nuclear Energy) after consultation with the Office of Security.

Advanced digital video surveillance for safeguard and physical protection

International Nuclear Information System (INIS)

Kumar, R.

2002-01-01

Full text: Video surveillance is a very crucial component in safeguard and physical protection. Digital technology has revolutionized the surveillance scenario and brought in various new capabilities like better image quality, faster search and retrieval of video images, less storage space for recording, efficient transmission and storage of video, better protection of recorded video images, and easy remote accesses to live and recorded video etc. The basic safeguard requirement for verifiably uninterrupted surveillance has remained largely unchanged since its inception. However, changes to the inspection paradigm to admit automated review and remote monitoring have dramatically increased the demands on safeguard surveillance system. Today's safeguard systems can incorporate intelligent motion detection with very low rate of false alarm and less archiving volume, embedded image processing capability for object behavior and event based indexing, object recognition, efficient querying and report generation etc. It also demands cryptographically authenticating, encrypted, and highly compressed video data for efficient, secure, tamper indicating and transmission. In physical protection, intelligent on robust video motion detection, real time moving object detection and tracking from stationary and moving camera platform, multi-camera cooperative tracking, activity detection and recognition, human motion analysis etc. is going to play a key rote in perimeter security. Incorporation of front and video imagery exploitation tools like automatic number plate recognition, vehicle identification and classification, vehicle undercarriage inspection, face recognition, iris recognition and other biometric tools, gesture recognition etc. makes personnel and vehicle access control robust and foolproof. Innovative digital image enhancement techniques coupled with novel sensor design makes low cost, omni-directional vision capable, all weather, day night surveillance a reality

Study on the development of safeguards information treatment system at the facility level

Energy Technology Data Exchange (ETDEWEB)

Lee, B. D.; Song, D. Y.; So, D. S.; Kwak, E. H. [KAERI, Taejon (Korea, Republic of)

2000-05-01

Safeguards Information Treatment System(SITS) at the facility level is required to implement efficiently the obligations under the Korea-IAEA Safeguards Agreement, bilateral agreements with other countries and domestic law. In this paper, the requirements and major functions of SITS were considered, and the error checking methods and the relationships of safeguards information were reviewed. SITS will be developed to cover the different accounting procedures and methods applied at the various facilities under IAEA safeguards. Also, the resolved result of the Y2K problem in the existing nuclear material accounting program was described.

Processing large sensor data sets for safeguards : the knowledge generation system.

Energy Technology Data Exchange (ETDEWEB)

Thomas, Maikel A.; Smartt, Heidi Anne; Matthews, Robert F.

2012-04-01

Modern nuclear facilities, such as reprocessing plants, present inspectors with significant challenges due in part to the sheer amount of equipment that must be safeguarded. The Sandia-developed and patented Knowledge Generation system was designed to automatically analyze large amounts of safeguards data to identify anomalous events of interest by comparing sensor readings with those expected from a process of interest and operator declarations. This paper describes a demonstration of the Knowledge Generation system using simulated accountability tank sensor data to represent part of a reprocessing plant. The demonstration indicated that Knowledge Generation has the potential to address several problems critical to the future of safeguards. It could be extended to facilitate remote inspections and trigger random inspections. Knowledge Generation could analyze data to establish trust hierarchies, to facilitate safeguards use of operator-owned sensors.

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.

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

Dynamic analysis of nuclear safeguards systems

International Nuclear Information System (INIS)

Wilson, J.R.; Rasmuson, D.M.; Tingey, F.H.

1978-01-01

The assessment of the safeguards/adversary system poses a unique challenge as evolving technology affects the capabilities of both. The method discussed meets this challenge using a flexible analysis which can be updated by system personnel. The automatically constructed event tree provides a rapid overview analysis for initial assessment, evaluation of changes, cost/benefit study and inspection and audit

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

The 50 Years of Safeguards and Non-Proliferation in Poland

International Nuclear Information System (INIS)

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

2015-01-01

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

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.

Exchange of pressurizer safeguarding system at Biblis nuclear power station

International Nuclear Information System (INIS)

Weber, D.; Hofbeck, W.

1991-01-01

Valves and piping of the pressurizer safeguarding system are exchanged and reset in such a way that they are suitable not only for discharging steam, but also for discharging a water-steam mixture and hot pressurized water; for the emergency measure of primary depressurization by hand (bleed) in the event of failure of the entire feedwater supply and station black-out, and in the event of operational transients with supposed failure of the reactor scram (ATWS). To achieve this, in addition to the requirements of the pressurizer discharging station, changes have to be made to the valve drive to dominate the water loads. During the 1990 inspection this exchange of the pressurizer discharging station was performed at the Biblis A unit as the first German plant. (orig.) [de

Signal estimation and change detection in tank data for nuclear safeguards

International Nuclear Information System (INIS)

Burr, Tom; Suzuki, Mitsutoshi; Howell, John; Longo, Claire E.; Hamada, Michael S.

2011-01-01

Process monitoring (PM) is increasingly important in nuclear safeguards as a complement to mass-balance based nuclear materials accounting (NMA). Typically, PM involves more frequent but lower quality measurements than NMA. While NMA estimates special nuclear material (SNM) mass balances and uncertainties, PM often tracks SNM attributes qualitatively or in the case of solution monitoring (SM) tracks bulk mass and volume. Automatic event marking is used in several nuclear safeguards PM systems. The aims are to locate the start and stop times and signal changes associated with key events. This paper describes results using both real and simulated SM data to quantify the errors associated with imperfect marking of start and stop times of tank events such as receipts and shipments. In the context of safeguards, one can look both forward and backward in modest time intervals to recognize events. Event marking methods evaluated include differencing, multi-scale principal component analysis using wavelets, and piecewise linear regression (PLR). All methods are evaluated on both raw and smoothed data, and several smoothing options are compared, including standard filters, hybrid filters, and local kernel smoothing. The main finding for real and simulated examples considered is that a two-step strategy is most effective. First, any reasonably effective initial smoother is used to provide a good initial guess at change point locations. Second, PLR is applied, looking for one change point at a time. In contrast, PLR that allows for multiple change points simultaneously has worse performance.

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

Review of potential technology contributions to safeguards

International Nuclear Information System (INIS)

Sellers, T.A.

1977-01-01

Separate, uncoordinated approaches to nuclear facility safeguards such as physical security and accounting are no longer adequate. A comprehensive, integrated strategy for improved in-depth protection of nuclear facilities with acceptable operational impact is needed. The safeguards system concept, analysis techniques, and hardware required to implement such a strategy are presented in this paper. Handbooks for intrusion detection, entry control systems, barrier, etc. are described briefly. 17 figures

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

Recommended observational skills training for IAEA safeguards inspections. Final report: Recommended observational skills training for IAEA safeguards inspections

International Nuclear Information System (INIS)

Toquam, J.L.; Morris, F.A.

1994-09-01

This is the second of two reports prepared to assist the International Atomic Energy Agency (IAEA or Agency) in enhancing the effectiveness of its international safeguards inspections through inspector training in open-quotes Observational Skillsclose quotes. The first (Phase 1) report was essentially exploratory. It defined Observational Skills broadly to include all appropriate cognitive, communications, and interpersonal techniques that have the potential to help IAEA safeguards inspectors function more effectively. It identified 10 specific Observational Skills components, analyzed their relevance to IAEA safeguards inspections, and reviewed a variety of inspection programs in the public and private sectors that provide training in one or more of these components. The report concluded that while it should be possible to draw upon these other programs in developing Observational Skills training for IAEA inspectors, the approaches utilized in these programs will likely require significant adaption to support the specific job requirements, policies, and practices that define the IAEA inspector's job. The overall objective of this second (Phase 2) report is to provide a basis for the actual design and delivery of Observational Skills training to IAEA inspectors. The more specific purposes of this report are to convey a fuller understanding of the potential application of Observational Skills to the inspector's job, describe inspector perspectives on the relevance and importance of particular Observational Skills, identify the specific Observational Skill components that are most important and relevant to enhancing safeguards inspections, and make recommendations as to Observational Skills training for the IAEA's consideration in further developing its Safeguards training program

Recommended observational skills training for IAEA safeguards inspections. Final report: Recommended observational skills training for IAEA safeguards inspections

Energy Technology Data Exchange (ETDEWEB)

Toquam, J.L.; Morris, F.A.

1994-09-01

This is the second of two reports prepared to assist the International Atomic Energy Agency (IAEA or Agency) in enhancing the effectiveness of its international safeguards inspections through inspector training in {open_quotes}Observational Skills{close_quotes}. The first (Phase 1) report was essentially exploratory. It defined Observational Skills broadly to include all appropriate cognitive, communications, and interpersonal techniques that have the potential to help IAEA safeguards inspectors function more effectively. It identified 10 specific Observational Skills components, analyzed their relevance to IAEA safeguards inspections, and reviewed a variety of inspection programs in the public and private sectors that provide training in one or more of these components. The report concluded that while it should be possible to draw upon these other programs in developing Observational Skills training for IAEA inspectors, the approaches utilized in these programs will likely require significant adaption to support the specific job requirements, policies, and practices that define the IAEA inspector`s job. The overall objective of this second (Phase 2) report is to provide a basis for the actual design and delivery of Observational Skills training to IAEA inspectors. The more specific purposes of this report are to convey a fuller understanding of the potential application of Observational Skills to the inspector`s job, describe inspector perspectives on the relevance and importance of particular Observational Skills, identify the specific Observational Skill components that are most important and relevant to enhancing safeguards inspections, and make recommendations as to Observational Skills training for the IAEA`s consideration in further developing its Safeguards training program.

Some Examples of the Relationship Between Containment and Other Engineered Safeguard Requirements, Accident Analyses and Site Conditions

Energy Technology Data Exchange (ETDEWEB)

Vinck, W. F.; Maurer, H. [EURATOM, Brussels (Belgium)

1967-09-15

The paper refers primarily to nuclear power reactors for which EURATOM has performed safety reviews in co-operation with national technical advisory organizations concerned in the licensing procedures. Comparative data are tabulated on a number of containment concepts and other engineered safeguards to protect against or to limit the consequences of major hypothetical accidents for a number of power reactors. Main environmental data, such as magnitudes of exclusion areas and population densities, are also presented. A number of topics of particular interest which were encountered during the safety analysis and which find widespread application in the assessment of the siting conditions and emergency planning are discussed. In this discussion, emphasis is placed on containment, engineered safeguards and emergency equipment. These items are considered in general with emphasis on: (a ) the importance of meeting operability and high efficiency requirements (reliability ) when needed through design and layout; (b) periodic testing and/or inspection possibilities and requirements in order to maintain high availability standards. Attention is drawn to some difficulties which have arisen in connection with design, material choice and construction of steel containment structures and which in the interests of safety as well as of economic optimization justify in the future more care in the use of possibly uniform or single-code requirements. Examples of uncertainties encountered in some accident analyses and their influence on siting considerations are discussed, with emphasis on safeguards intended to retain radioactive material in the plant, such as extent of core damage, iodine plate-out, filtering efficiency, wash-out effects. The means by which some of the main uncertainties have been or can in the future be eliminated through appropriate experimental programmes performed throughout the world are discussed. Some examples are also given of the influence of factors which

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)

Strengthened safeguards: Present and future challenges

International Nuclear Information System (INIS)

Goldschmidt, Pierre

2001-01-01

the tasks of implementing traditional safeguards. New tasks are appearing; a significant recent example is the consequence, for the Department's Security of Material Programme, of the September terrorist attacks in the United States. The gap between what is required and the available resources cannot continue to increase indefinitely. (author)

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)

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

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

Non-proliferation and safeguards in South Africa

International Nuclear Information System (INIS)

Broodryk, Alta

2001-01-01

South Africa occupies a unique position in the history of the Non-Proliferation Treaty in being the only country with a nuclear weapons capability that was voluntary terminated before acceding to the Treaty. The first nuclear device built was completed in December 1982, five more devices followed at an orderly pace of less than one per year and on 26 February 1990 cabinet officially implemented the termination of its nuclear deterrent capability. The events that flowed from the termination was that South Africa: Acceded to the Non-Proliferation Treaty (10 July 1991); Signed Comprehensive Safeguards Agreement, INFCIRC/394, (16 September 1991); Submitted its initial inventory of nuclear material (30 September 1991); and Received first verification team from the Agency (November 1991). South Africa, being dedicated to the prevention of the proliferation of Nuclear Weapons became a party to various non-proliferation treaties, regimes and groups. The National Non- Proliferation Policy, as published in a Cabinet memorandum, also clearly states this commitment. To comply with the requirements of the Treaty and Agreement the following two acts were published: The Nuclear Energy Act; The Non-Proliferation of Weapons of Mass Destruction Act. The Minister of Minerals and Energy is the State Authority for the implementation of the Safeguards Agreement in South Africa, however, the Minister delegated this Authority to NECSA's Safeguards Division. To implement the requirements of the various acts, control regimes and treaties a State System for Accounting and Control of Nuclear Material, based on the ISO 9001:2000 standard, was designed. This standard focuses on customer satisfaction, continuous improvement, the demonstration of commitment and the prevention of non-conformity. To comply with the requirements of the standard the following procedures were established and maintained: A Quality Manual; Customer focus; Control of documents; Control of quality records; Internal Audits

Safeguards sealing systems for Zebra

International Nuclear Information System (INIS)

Ingram, G.; Jamieson, G.R.

1983-01-01

A relatively simple design has been produced for safeguards seals to be applied throughout the fuel containing areas at Zebra. It is based on the use of wire seals and regular Inspector surveillance. The application of the system would allow an Inspector to establish to a high degree of confidence that significant quantities of fuel had not been diverted during an intensive experimental programme. It would add about 5% to the time required for experiments, and careful planning would reduce this value. The inspection effort required to witness element movements during the experimental programme would average about 2 hours per day, with a further 2 hours spent each week on NDA of the fuel exposed. The Safeguards Inspector would require to spend about 25% of his time in the reactor area and would have ample time to deal with the relatively small number of fuel movements taking place in the storage area and with his duties elsewhere in the plant. During a core change, full-time inspection effort would be required for about 6 weeks each year. (author)

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

Protection of unclassified safeguards information; criteria and guidance

International Nuclear Information System (INIS)

Kasun, D.J.

1981-10-01

The document was prepared to assist licensees and other persons who possess unclassified safeguards information in establishing an information protection system that satisfies the requirements of 10 CFR 73.21. Section 73.21 was issued by the Nuclear Regulatory Commission in response to the provisions of a new Section 147 of the Atomic Energy Act of 1954, as amended, titled Safeguards Information

Safeguards and security progress report, January-December 1983

Energy Technology Data Exchange (ETDEWEB)

Smith, D.B. (comp.)

1984-09-01

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

Safeguards and security progress report, January-December 1983

International Nuclear Information System (INIS)

Smith, D.B.

1984-09-01

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

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.

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)

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.

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)

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)

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)

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 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

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

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

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

Safeguarding of spent fuel conditioning and disposal in geological repositories

International Nuclear Information System (INIS)

Forsstroem, H.; Richter, B.

1997-01-01

Disposal of spent nuclear fuel in geological formations, without reprocessing, is being considered in a number of States. Before disposal the fuel will be encapsulated in a tight and corrosion resistant container. The method chosen for disposal and the design of the repository will be determined by the geological conditions and the very strict requirements on long-term safety. From a safeguards perspective spent fuel disposal is a new issue. As the spent fuel still contains important amounts of material under safeguards and as it can not be considered practicably irrecoverable in the repository, the IAEA has been advised not to terminate safeguards, even after closure of the repository. This raises a number of new issues where there could be a potential conflict of interests between safety and safeguards demands, in particular in connection with the safety principle that burdens on future generations should be avoided. In this paper some of these issues are discussed based on the experience gained in Germany and Sweden about the design and future operation of encapsulation and disposal facilities. The most important issues are connected to the required level of safeguards for a closed repository, the differences in time scales for waste management and safeguards, the need for verification of the fissile content in the containers and the possibility of retrieving the fuel disposed of. (author)

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

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.

Optimizing the IAEA safeguards system

International Nuclear Information System (INIS)

Drobysz, Sonia; Sitt, Bernard

2011-09-01

reluctant to bear the burden of it. Optimization can also weaken the argument according to which States should not accept new obligations while others are not committed to the existing ones, since 'new obligations' finally result in more effective and efficient verification scheme, benefiting to both States and the Agency. The current evolution of the safeguards system tending to better allocate safeguards activities and resources, doing away with a quantitative approach and promoting qualitative, customized implementation of safeguards is reviewed in Chapter 2. The latter suggests that despite ongoing and positive efforts, remaining difficulties slow down the move to a real 'analytical' or 'factors' driven system. Chapter 3 therefore looks at ways to overcome weaknesses in safeguards approaches, institutional and collaborative practices, in order to develop safeguards resources and measures where the proliferation risk lies and not necessarily on States with large nuclear power and industries. In that sense, optimization implies targeting verification. Three main interconnected tracks are suggested: enhanced selectiveness of verification efforts could be based on a more flexible application of safeguards allowing for transparency and openness dividends; it would require improved institutional transparency; finally, it could be supported by furthering cooperation both at the regional level and with relevant international organisations. (author)

Evolution of a safeguards support program: POTAS past and future

International Nuclear Information System (INIS)

Kessler, J.C.; Reisman, A.W.

1992-01-01

When the Non-Proliferation Treaty came into force, the International Atomic Energy Agency (IAEA) became for the first time responsible for implementing full-scope safeguards in many countries, including countries with large and sophisticated nuclear programs. The IAEA's Department of Safeguards did not have the safeguards technology appropriate for these rapidly expanding responsibilities, nor did it have a research and development program to respond to that need. In response to this situation, the United States initiated the US Program of Technical Assitance to IAEA Safeguards (POTAS) in 1977. This program was originally intended to be a 5-yr, $5 million program. As the United States and the IAEA began to implement this program, several things rapidly became clear. Meeting the evolving safeguards technology needs would require much more than $5 million; within the first 5 yr, the United States allocated more than $20 million. This paper summarizes the policies activities, and practices POTAS has employed in support of IAEA safeguards program

Preliminary considerations on developing IAEA technical safeguards for LMFBR power systems

International Nuclear Information System (INIS)

Persiani, P.J.

1980-09-01

Nuclear fuel cycles safeguards should be considered in the dynamic context of a world deployment of various reactor types and varying availability of fuel-cycle services. There will be a close interaction between thermal-reactor cycles and the future deployment of fast breeders. The quantitites of plutonium and the reprocessing, conversion, fabrication, and storage methods of the fuel for the fast breeders will have a significant impact on safeguards techniques. The approach to the fast breeder fuel cycle safeguards follows the general safeguards system approach proposed by the IAEA. Objective of IAEA safeguards is the detection of diversion of nuclear material and deterrence of such diversion. To achieve independent verification of material balance accountancy requires the capability to monitor inventory status and verify material flows and quantities of all nuclear materials subject to safeguards. Containment and surveillance measures are applied to monitor key measurement points, maintain integrity of material balance, and complement material accountancy. The safeguards study attempts to develop a generic reference IAEA Safeguards System and explores various system options using containment/surveillance and material accountancy instrumentation and integrated systems designs

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

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

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

International Nuclear Information System (INIS)

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

1993-01-01

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

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)

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)

Safeguards equipment of the future integrated monitoring systems and remote monitoring

International Nuclear Information System (INIS)

Sonnier, C.S.; Johnson, C.S.

1994-01-01

Becoming aware of the significant events of the past four years and their effect on the expectations to international safeguards, it is necessary to reflect on which direction the development of nuclear safeguards in a new era needs to take and the implications. The lime proven monitoring techniques, based on quantitative factor's and demonstrated universal application, have shown their merit. However, the new expectations suggest a possibility that a future IAEA safeguards system could rely more heavily on the value of a comprehensive, transparent and open implementation regime. Within such a regime, the associated measures need to be determined and technological support identified. This paper will identify the proven techniques which, with appropriate implementation support, could most quickly make available additional measures for a comprehensive, transparent and open implementation regime. In particular, it will examine the future of Integrated Monitoring Systems and Remote Monitoring in international safeguards, including technical and other related factors

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.

Integrated safeguards: Australian views and experience

International Nuclear Information System (INIS)

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

2001-01-01

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

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.

Recent developments in the implementation of Euratom safeguards

International Nuclear Information System (INIS)

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

1983-01-01

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

Potential development of non-destructive assay for nuclear safeguards

International Nuclear Information System (INIS)

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

1983-01-01

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

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

International Nuclear Information System (INIS)

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

1983-01-01

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

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

International safeguards concerns of Spent Fuel Disposal Program

International Nuclear Information System (INIS)

Pillay, K.K.S.

1988-01-01

The purpose of this paper is to stimulate discussions on the subjects of safeguarding large quantities of plutonium contained in spent fuels to be disposed of in geologic respositories. All the spent fuel disposal scenarios examined here pose a variety of safeguards problems, none of which are adequately addressed by the international safeguards community. The spent fuels from once-through fuel cycles in underground repositories would become an increasingly attractive target for diversion because of their plutonium content and decreasing radioactivity. Current design of the first geologic repository in the US will have the capacity to accommodate wastes equivalent to 70,000 Mt of uranium from commercial and defense fuel cycles. Of this, approximately 62,000 Mt uranium equivalent will be commerical spent fuel, containing over 500 Mt of plutonium. International safeguards commitments may require us to address the safeguards issues of disposing of such large quanities of plutonium in a geologic repository, which has the potential to become a plutonium mine in the future. This paper highlights several issues that should be addressed in the near term by US industries and the DOE before geologic repositories for spent fuels become a reality

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

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

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 and technical support programs: POTAS in the 1990s

International Nuclear Information System (INIS)

Kessler, C.J.

1991-01-01

The US Program of Technical Assistance to IAEA Safeguards (POTAS) has since 1978 provided technology and technical assistance to the IAEA to support its nuclear safeguards activities. The present level of support, $6.9 million per year, equals 10% of the Department of Safeguards annual budget. During the next decade, the International Atomic Energy Agency (IAEA) will face new technical challenges in carrying out its verification activities. To help the IAEA acquire the technology and other technical support that it will require in the 1990s, POTAS expects to continue its assistance, both in the areas established in the past and in additional areas dictated by newly identified IAEA safeguards requirements. This paper will look at the political and policy context within which the Department of Safeguards, and hence POTAS, operates, and how that context is expected to evolve over the next decade. The roles and functions of POTAS will be identified and discussed in terms of their historical evolution. Lastly, the paper will consider how POTAS is expected to change during the 1990s, both to maintain effectiveness in existing roles and functions, and to meet the challenge of the changing policy context. 5 refs

Influence of safeguards and fire protection on criticality safety

International Nuclear Information System (INIS)

Six, D.E.

1980-01-01

There are several positive influences of safeguards and fire protection on criticality safety. Experts in each discipline must be aware of regulations and requirements of the others and work together to ensure a fault-tree design. EG and G Idaho, Inc., routinely uses an Occupancy-Use Readiness Manual to consider all aspects of criticality safety, fire protection, and safeguards. The use of the analytical tree is described

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

Accountability and Transparency: Essential Underpinnings of Quality Safeguards

International Nuclear Information System (INIS)

Everton, C.; Floyd, R.

2015-01-01

The fundamental purpose of IAEA safeguards is to maintain confidence in the international community of the compliance of States with their respective non-proliferation commitments. The safeguards system for ensuring this compliance produces the most important output, the IAEA's compliance findings. Confidence in the findings of any compliance verification system requires some basic elements such as independence, accountability, transparency, and quality management systems. Quality management systems are an internal set of documents and procedures that, while clearly important, need to incorporate an external communication component in order to engender confidence as to how compliance is being managed and ensured. This paper will explore the importance of these fundamentals to confidence in IAEA safeguards compliance conclusions, with a focus on the external communication elements of accountability and transparency. Accountability and transparency will be considered with different communication channels through which safeguards implementation matters are explained and reported and at different levels, facility, State, regional, and the IAEA. This will include communications by: the IAEA and State authorities to the general public; State authorities to peers in other national safeguards authorities (regional and beyond); and, the IAEA and State authorities to the international community as represented through the Board of Governors and General Conference. Examples will be presented of good practices in these areas to encourage greater accountability and transparency in the work of safeguards. (author)

Safeguards against Takeover after Volkswagen

DEFF Research Database (Denmark)

Werlauff, Erik

2009-01-01

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

Computerization of the safeguards analysis decision process

International Nuclear Information System (INIS)

Ehinger, M.H.

1990-01-01

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

The Office of Safeguards and Security Nonproliferation Support Program

International Nuclear Information System (INIS)

Desmond, W.J.

1996-01-01

The Nonproliferation Support Program was established in the Department of Energy, Office of Safeguards and Security on october 1, 1995. its mission includes providing assistance to Departmental efforts for improved international material protection, control and accounting programs by coordinating and leveraging domestic safeguards and security policy, practice and experience into the international arena. A major objective of the program is to balance US national security requirements with global support of the nonproliferation objectives. This paper describes the organization of the Office of Safeguards and Security and the Nonproliferation Support Program role and responsibility, and presents some of the current areas of program emphasis and activity

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

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

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.

The SSAC in international safeguards and non-proliferation aspects

International Nuclear Information System (INIS)

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

1989-01-01

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

Evaluation of safeguards inspection techniques--a time for change

International Nuclear Information System (INIS)

Anon.

1977-01-01

The adequacy of safeguards is a subject of highest concern--not only to the public and the government but to the nuclear community as a whole. The unusual nature of safeguards with its potential for risk, even to hypothetical and severe threats which have never occurred but are nevertheless being postulated, requires that the highest attention be given. It is with this thought in mind that this paper was written to endorse a new approach to safeguards which not only permits more flexibility for the industry but in large measure should provide a significantly increased assurance to the public and to the world that the nuclear industry can safeguard plutonium and other strategic nuclear material in a fully acceptable manner. The costs of these changes will undoubtedly be high. However, the benefits to be derived from the long-term utilization of nuclear resources, such as those embodied in plutonium, will more than compensate for these additional costs. It may be only with such strict attention to safeguards that the long-term nuclear option will be permitted to prevail

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

Non-proliferation of nuclear weapons and nuclear security. IAEA safeguards agreements and additional protocols

International Nuclear Information System (INIS)

Lodding, Jan; Kinley, David III

2002-09-01

One of the most urgent challenges facing the International Atomic Energy Agency (IAEA) is to strengthen the Agency's safeguards system for verification in order to increase the likelihood of detecting any clandestine nuclear weapons programme in breach of international obligations. The IAEA should be able to provide credible assurance not only about declared nuclear material in a State but also about the absence of undeclared material and activities. Realising the full potential of the strengthened system will require that all States bring into force their relevant safeguards agreements, as well as additional protocols thereto. Today, 45 years after the Agency's foundation, its verification mission is as relevant as ever. This is illustrated by the special challenges encountered with regard to verification in Iraq and North Korea in the past decade. Moreover, the horrifying events of 11 September 2001 demonstrated all too well the urgent need to strengthen worldwide control of nuclear and other radioactive material. The IAEA will continue to assist States in their efforts to counter the spread of nuclear weapons and to prevent, detect and respond to illegal uses of nuclear and radioactive material. Adherence by as many States as possible to the strengthened safeguards system is a crucial component in this endeavour

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

Design measures to facilitate implementation of safeguards at future water cooled nuclear power plants

International Nuclear Information System (INIS)

1999-01-01

The report is intended to present guidelines to the State authorities, designers and prospective purchasers of future water cooled power reactors which, if taken into account, will minimize the impact of IAEA safeguards on plant operation and ensure efficient and effective acquisition of safeguards data to the mutual benefit of the Member State, the plant operator and the IAEA. These guidelines incorporate the IAEA's experience in establishing and carrying out safeguards at currently operating nuclear power plants, the ongoing development of safeguards techniques and feedback of experience from plant operators and designers on the impact of IAEA safeguards on plant operation. The following main subjects are included: The IAEA's safeguards function for current and future nuclear power plants; summary of the political and legal foundations of the IAEA's safeguards system; the technical objective of safeguards and the supply and use of required design information; safeguards approaches for nuclear power plants; design implications of experience in safeguarding nuclear power plants and guidelines for future water cooled reactors to facilitate the implementation of safeguards

Safeguards and security. Progress report, August 1982-January 1983

International Nuclear Information System (INIS)

Smith, D.B.

1983-11-01

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

Safeguards and security status report, August 1981-January 1982

Energy Technology Data Exchange (ETDEWEB)

Shipley, J.P. (comp.)

1982-09-01

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

Safeguards and security status report, August 1981-January 1982

International Nuclear Information System (INIS)

Shipley, J.P.

1982-09-01

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

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.

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

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

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

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

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

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

International Nuclear Information System (INIS)

2008-06-01

commonly used, for instance, in shielding on radioactive sources used in hospitals. Other radioactive material, such as most radioactive sources and isotopes used in medicine, industry, agriculture, and water resource management, are not the subject of safeguards and need not be reported to the IAEA under safeguards agreements. Reporting depends on the level of nuclear activity in the country. Declarations pursuant to safeguards agreements and additional protocols for States that do not have nuclear facilities are expected to be short and simple. The IAEA has prepared a document, available upon request, which provides guidance on the reporting requirements for such States. More elaborate guidelines have been prepared for States that do have nuclear facilities subject to routine safeguards inspections. Through its activities in the field, the IAEA seeks to verify the correctness and completeness of States' reports and declarations regarding nuclear material. Each State with a comprehensive safeguards agreement is required to establish and maintain a State system of accounting for and control of nuclear material (SSAC), which is the national authority formally designated to keep track of nuclear material and activities in the country. For all States with safeguards agreements in force, the IAEA draws an annual conclusion on the non-diversion of nuclear material and other items placed under safeguard. The IAEA's focal point for the negotiation of safeguards agreements and additional protocols, and the amendment of SQPs, is the Office of External Relations and Policy Coordination. Once a State has decided to conclude such an agreement and/or protocol, or amend its SQP, the IAEA can help the country with the implementation of related legal and technical requirements. The appendix of this publication informs how to conclude a comprehensive Safeguards Agreement and/or an Additional Protocol and provides 3 model notification letters for (a) conclusion of a safeguards agreement, a

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

International Nuclear Information System (INIS)

2008-04-01

commonly used, for instance, in shielding on radioactive sources used in hospitals. Other radioactive material, such as most radioactive sources and isotopes used in medicine, industry, agriculture, and water resource management, are not the subject of safeguards and need not be reported to the IAEA under safeguards agreements. Reporting depends on the level of nuclear activity in the country. Declarations pursuant to safeguards agreements and additional protocols for States that do not have nuclear facilities are expected to be short and simple. The IAEA has prepared a document, available upon request, which provides guidance on the reporting requirements for such States. More elaborate guidelines have been prepared for States that do have nuclear facilities subject to routine safeguards inspections. Through its activities in the field, the IAEA seeks to verify the correctness and completeness of States' reports and declarations regarding nuclear material. Each State with a comprehensive safeguards agreement is required to establish and maintain a State system of accounting for and control of nuclear material (SSAC), which is the national authority formally designated to keep track of nuclear material and activities in the country. For all States with safeguards agreements in force, the IAEA draws an annual conclusion on the non-diversion of nuclear material and other items placed under safeguard. The IAEA's focal point for the negotiation of safeguards agreements and additional protocols, and the amendment of SQPs, is the Office of External Relations and Policy Coordination. Once a State has decided to conclude such an agreement and/or protocol, or amend its SQP, the IAEA can help the country with the implementation of related legal and technical requirements. The appendix of this publication informs how to conclude a comprehensive Safeguards Agreement and/or an Additional Protocol and provides 3 model notification letters for (a) conclusion of a safeguards agreement, a

Structure and drafting of safeguards regulatory documents

International Nuclear Information System (INIS)

Cole, R.J.; Bennett, C.A.; Edelhertz, H.; Wood, M.T.; Brown, R.J.; Roberts, F.P.

1977-09-01

This study develops hypothesis about the relation between the structure and drafting of safeguards regulatory documents and the ability of document users to understand and implement them in a way that reflects the intent and requirements of the NRC. Four decisions are needed to improve communication: (1) Should improvement of safeguards regulatory documents as communication instruments be an explicit NRC program. (2) What specific methods of communication should be the focus of improvement efforts. (3) What actions to improve communications are feasible and desirable. (4) How should the NRC divide its available effort and resources among desirable actions in order to provide the most effective communication through regulatory documents. This volume contains: introduction, conceptual bases, legal requirements, targets, choice of documents, preparation of documents, readability, and further study of recommended changes in structure and drafting

Current trends in the implementation of IAEA safeguards

International Nuclear Information System (INIS)

Adamson, A.; Bychkov, V.

1993-01-01

A practical goal, embodying the principle that a minimum amount of material is required in order to manufacture a nuclear explosive device, is that safeguards activities should enable the timely detection of the diversion of a significant quantity of nuclear material. It is important to note that the safeguards activities are not restricted to the International Atomic Energy Agency (the agency) but impose obligations on both state (and consequently on facility operators) and the agency. The beneficiaries are member states of the world community which have enhanced confidence in the competence and probity of states with safeguards agreements. Neither safeguards nor the nuclear industry have remained stationary. As new techniques have been developed, they have found applications, and as new challenges were encountered, the system has responded, for example, through improved measurements; through new or improved techniques for the operator, state or agency; and through new regulations. This paper details approaches, procedures and techniques developed for new complex nuclear facilities. Trends toward increase efficiency and effectiveness, and developments leading to more automated analysis and collection of data and the development of nondestructive assay methods are examined. Also important are trends in the presentation of safeguards results to the states and the general public

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

The DOE safeguards and security technology development program

International Nuclear Information System (INIS)

Cherry, R.C.; Wheelock, A.J.

1991-01-01

This paper reports that strategic planning for safeguards and security within the Department of Energy emphasizes the contributions of advanced technologies to the achievement of Departmental protection program goals. The Safeguards and Security Technology Development Program provides state-of-the-art technologies, systems and technical services in support of the policies and programmatic requirements for the protection of Departmental assets. The Program encompasses research and development in physical security, nuclear material control and accountability, information security and personnel security, and the integration of these disciplines in advanced applications. Technology development tasks serve goals that range from the maintenance of an effective technology base to the development, testing and evaluation of applications to meet field needs. A variety of factors, from the evolving threat to reconfiguration of the DOE complex and the technical requirements of new facilities, are expected to influence safeguards and security technology requirements and development efforts. Implementation of the Program is based on the systematic identification, prioritization and alignment of technology development tasks and needs. Initiatives currently underway are aimed at enhancing technology development project management. Increased management attention is also being placed on efforts to promote the benefits of the Program through technology transfer and interagency liaison

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.

Assurance of the effectiveness of safeguards in light of their objectives

International Nuclear Information System (INIS)

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

1977-01-01

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

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

A data management system for safeguards applications (DMSSA)

International Nuclear Information System (INIS)

Wu Yuan

1994-09-01

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

A data management system for safeguards applications (DMSSA)

Energy Technology Data Exchange (ETDEWEB)

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

1994-09-01

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

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)

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

International Nuclear Information System (INIS)

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

1993-07-01

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

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

Prioritizing and scheduling Portsmouth Gaseous Diffusion Plant safeguards upgrades

International Nuclear Information System (INIS)

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

1992-02-01

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

Activities of special committee on 'quality assurance of accountancy analysis for safeguards'

International Nuclear Information System (INIS)

2010-01-01

For the long-term stable operation of nuclear fuel cycle facilities, it is essential to satisfy the requirements of IAEA safeguards agreement. It could be attained by precise implementation of accountancy analysis of nuclear materials and application of Destructive Analysis (DA) which enables highly precise measurement is necessary. The requirements to maintain and improve the precision of DA are supposed to grow along with nuclear fuel cycle fully in progress and Pu handling amount increases. In order to maintain long-term stability of quality level of accountancy analysis for safeguards, a special committee on 'Quality Assurance (QA) for Accountancy /Safeguards analysis' was established at Atomic Energy Society Japan supported by INNM-Japan Chapter. Experts of safeguards analysis, reference materials, statistics and QA were gathered and drafted the committee standard document for isotope dilution mass spectrometry, the major accountancy analysis technique for Pu and U, supported Pu standard preparation at JAEA and summarized the items needed for QA of DA. (author)

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

Energy Technology Data Exchange (ETDEWEB)

Forland, A.

1997-12-31

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

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

Energy Technology Data Exchange (ETDEWEB)

Forland, A

1998-12-31

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

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

International Nuclear Information System (INIS)

Forland, A.

1997-01-01

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

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

Policy and technical issues for international safeguards in nuclear weapons states

International Nuclear Information System (INIS)

Markin, J.T.; Stanbro, W.D.

1994-01-01

Expansion of international safeguards into the military and commercial fuel cycles of the nuclear weapons states (NWS) -- the subject of previous proposals in international safeguards discussions and of studies in the safeguards literature -- has been given impetus by recent US government initiatives for safeguards on excess weapons materials and a verified fissile materials production cutoff. These proposals, if implemented, would have implications on the safeguards objectives, approaches, and technologies that are traditionally employed in international safeguards. This paper examines the modifications and innovations that might be required to the current international safeguards regime in meeting these proposed new roles. Although the examples given are in the context of the US materials and facilities, many of the conclusions are valid for other NWS. None of the statements in this paper represent official US position on policy for international safeguards in weapons states. Instead, the purpose is to identify policy and technical issues and to offer, where possible, options for their resolution. This paper limits consideration to the potential role of the IAEA in verifying these proposed initiatives for declared facilities, recognizing that there may also be a role for bilateral, multilateral, or regional verification regimes. Indeed, in some cases verification of weapons materials may be more appropriate for a bilateral arrangement. Because traditional IAEA safeguards may not be admissible for weapons materials, the concept of ''transparency'' is suggested as a less intrusive alternative providing some confidence that materials are as declared

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.

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

International Nuclear Information System (INIS)

1987-07-01

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

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.

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

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.

U.S. next generation safeguards initiative: the human capital development program

International Nuclear Information System (INIS)

Scholz, M.A.

2013-01-01

The Human Capital Development (HCD) subprogram of the U.S. Next Generation Safeguards Initiative (NGSI) is developing sustainable academic and technical programs that support the recruitment, education, training, and retention of the next generation of international safeguards professionals. This wide-ranging HCD effort endeavors to develop additional human resources to address current shortfalls, encourage U.S. experts to seek employment at the IAEA, and identify and train a new cadre of safeguards experts to meet the needs of both the United States and the IAEA for decades to come. In recent years, a convergence of factors has challenged the IAEA's ability to carry out its safeguards mission effectively. A staffing study shows that less than 20% of the international safeguards specialists in the U.S. workforce are 44 years of age or younger and that over 80% of the international safeguards specialists at the National Laboratories will be retired or otherwise resigned within 15 years. An aging workforce nearing retirement and growing workload, coupled with a safeguards budget that has remained essentially flat in real terms for nearly two decades, have posed particular challenges to the IAEA's Department of Safeguards. Recognizing the trends, the National Nuclear Security Administration's (NNSA) Office of Nonproliferation and International Security (NIS) launched NGSI in the fall of 2007. Since that time, the HCD subprogram of NGSI has sponsored over 300 safeguards internships at U.S. National Labs, organized eight annual short safeguards policy and technical courses, worked with ten universities to develop new undergraduate and graduate course-work on international safeguards and nonproliferation, established a highly competitive graduate fellowship program, and completed a human capital requirements study that closely examined the safeguards workforce within the U.S. National Lab complex. Of past NGSI students and interns, nearly four in ten pursue multiple NGSI

A study on the national safeguards system -Current status and suggested development-

International Nuclear Information System (INIS)

Park, Wan Su; Kwack, Eun Ho; An, Jong Sung; Kim, Hyun Tae; Min, Kyung Sik; Park, Chan Sik

1995-03-01

In Korea, 17 nuclear facilities are currently under IAEA's safeguards and it is expected that more than 25 nuclear facilities will be under IAEA's safeguards in the year 2000 according to nuclear R and D and industry expansion. In connection with unlimited extension of NPT in 1995 and IAEA's measures to strengthen the safeguards like 'Programme 93+2', the international non-proliferation regime will be strengthened more and nuclear advanced countries will require the transparency and credibility of nuclear activities in recipient countries instead of transferring advanced nuclear technologies and nuclear material. In 1995, the Korean government had revised the Atomic Energy Law to control increasing nuclear facilities and nuclear material effectively and to establish international transparency and credibility. In the revised Atomic Energy Law, it is provided that the national inspection, other than IAEA inspection, will be started from 1996. Currently, necessary arrangements for national inspection are being prepared by MOST and TCNC at KAERI. However, the safeguards system in Korea is still beginning stage, Korea's safeguards activity was passive and fragmentary that leads non-attainment of safeguards goal in many facilities. The reasons were; absence of systematic safeguards system (SSAC); lack of understanding safeguards concepts; lack of manpower, designated organization for safeguards, etc. As Korea ranked world top 10 nuclear power generation country and has a plan to be a nuclear advanced country, Korea should have appropriate safeguards system and should not spare necessary assistance to that system. 14 tabs., 15 figs., 29 refs. (Author)

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

Commercial-off-the-shelf digital surveillance systems for safeguards

International Nuclear Information System (INIS)

Neufing, C.; Tschritter, C.; Meylemans, P.; Vandaele, R.; Heppleston, M.; Chare, P.; Kloeckner, W.

2001-01-01

The reasons why safeguards authorities are from time to time looking for Commercial-Off-The-Shelf (C.O.T.S.) equipment for safeguards purposes are for the following reasons: Equipment that is designed from scratch to satisfy specific safeguards requirements is very likely to go through a period of teething problems. If these problems are only discovered once the equipment is deployed for routine use, this will be accompanied with large overhead costs for the safeguards authorities to maintain and repair such equipment. The overhead costs are much higher if unattended equipment is concerned that is permanently installed on-site. In that case an extra mission has to be organised to return the faulty equipment to our headquarters before it can be repaired. Using C.O.T.S. equipment that is also used by others reduces the risk of teething problems. At least the burden of going through such kind of problem period is shared with other customers of the concerned equipment. It is clear that safeguards is not a big market on its own. The non-negligible cost of the development of equipment that only fits safeguards requirements will therefore have to be recovered on the expected sales. If the market is small, if the expected number of units that can be sold is small, a large part of the unit cost will depend on the initial development costs. Going for C.O.T.S. equipment that is also sold in other markets, would in that respect lower the equipment cost. That not any safeguards equipment can be obtained commercially off the shelf is clear, but in certain domains like digital surveillance, the functionality of C.O.T.S. equipment has been approaching the one needed for safeguards. That is why in 1998 the Euratom Safeguards Office published an open call for tender for the purchase of a digital surveillance system that is able to support up to 64 colour camera channels. In response to a successful bid for this call for tender a contract for the delivery of 3 prototype systems and 6

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)'

Safeguards Considerations for the Design of a Future Fast Neutron Sodium Cooled Reactor

International Nuclear Information System (INIS)

Cazalet, J.; Raymond, P.; Masson, M.; Saturnin, A.

2015-01-01

Incorporating safeguards at an early stage of a reactor design is a way to increase the effectiveness and efficiency of safeguards measures minimizing the possibilities of misuse of the plant or nuclear material diversion. It also reduces the impact on the construction and operation cost. At the preliminary phase, the design will integrate: confinement, containment, surveillance features and non-destructive assay equipment. Taking into account these requirements will help the operator in the approval of the plant at the design phase by national and international authorities in charge of Nuclear Material accounting and safeguards. A large amount of work has been made by the GEN IV International Forum to assess the proliferation resistance of nuclear systems. The IAEA has developed guidelines on ''Safeguards by design'' describing reference requirements for future nuclear facilities. Based on these studies, this communication details implementation of safeguards in the design of a sodium cooled fast neutron reactor (SFR) currently studied in France. Specificities are the use of MOX fuel with high concentration of plutonium and the potential capacity of breeding. A great attention should be paid to avoid diversion of nuclear material contained in fresh or irradiated fuel. Scenarios of reactor misuse are analyzed. The identification of diversion pathways and requirements for nuclear material accountancy, leads to an approach of safeguards, specific to SFR: Material Balance Areas (MBA) and some key measurement points (KMP) are characterized. Specific instrumentation assay helping in the identification and/or characterization of fuel elements and the inventory of nuclear material is described. As concerns the fuel cycle, the safeguards of the reprocessing unit will be progressively increased through the development of materials monitoring and the implementation of these measures at strategic locations of buildings, thus providing real-time information

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

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

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

International Nuclear Information System (INIS)

Woo, Tae-Ho; Lee, Un-Chul

2011-01-01

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

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.

Information required from States, including 'small quantities protocol' status, under the Protocol Additional to Safeguards Agreements

International Nuclear Information System (INIS)

Tuley, N.

1999-01-01

The Model, or Additional, Protocol to the Model Safeguards Agreement, INFCIRC/153, contains, inter alia, provisions for expanded declarations from Member States to the IAEA. These provisions include earlier design information declarations and information on fuel cycles activities, such a mining and milling, that were not previously part of safeguards. The session discusses the extent of the expanded declarations and provides examples of the forms that will be used to provide the information to the Agency. (author)

Development of an advanced safeguards system as a proliferation deterrent

International Nuclear Information System (INIS)

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

1978-11-01

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

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)

Equipment support for the implementation of safeguards

International Nuclear Information System (INIS)

Arlt, R.; Bosler, G.; Goldfarb, M.; Schanfein, M.; Whichello, J.

2001-01-01

Full text: The provision of effective, reliable, and user-friendly equipment needed for the implementation of safeguards is one of the main objectives of the Division of Technical Services (SOTS) in the Department of Safeguards. As an outcome of a review by an independent external consultant firm, the instrumentation sections of the SGTS were reorganized in January 2001 into two new sections, the Section for NDA Systems and Seals (TNS) and Section for Installed Systems (TIE). Each section has 'cradle-to-grave' responsibilities for development, implementation, maintenance, and decommissioning of safeguards instruments and measurement systems. Unattended assay, monitoring and surveillance instruments are the responsibility of TIE while attended nondestructive assay (NDA) instruments and seals are handled by TNS. The principal goals of both sections are to define equipment requirements based on Departmental needs, to coordinate Support Programme tasks concerning development and implementation activities, to provide system engineering of commercial components, manage laboratory and to do field testing and prove system suitability for defined safeguards applications. In addition both sections coordinate equipment and supply needs for the Department, including acquisition, preparation, servicing, installation, commissioning, troubleshooting, maintenance and repair, ensuring their availability when needed. As required, TIE and TNS provide specialized field support to the Operations Divisions. Each section is working to standardize equipment as much as possible and reduce the number of instruments performing the same function. This reduces both inspector and technician training, required parts inventories, and overall life-cycle costs. Development based on User Needs from the Operations Divisions follows a strict quality control program that includes a thorough qualification testing procedure with the last phase being field-testing under actual facility conditions. A

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

The IAEA inspectorate, including new requirements

International Nuclear Information System (INIS)

Alston, W.

1998-01-01

The basic purpose of the IAEA safeguards system is 'timely detection of diversion of significant quantities of nuclear material'. Safeguards implementation is regulated by the IAEA Statute and individual safeguards agreements. The IAEA Inspectorate and its scope are described together with the technical objectives and the concept of verification. Effective implementation of safeguards requires cooperation between the IAEA and the state concerned. To this end, agreements require that the State should establish and maintain a system of accounting for and control of nuclear material subject to safeguards. The IAEA safeguards system has demonstrated a flexibility capable of responding to the verification demands of Member States. Is is capable of safeguarding nuclear materials, facilities, equipment and non-nuclear material. The IAEA is in the process of strengthening safeguards in its verification of declared activities

The IAEA inspectorate, including new requirements

Energy Technology Data Exchange (ETDEWEB)

Alston, W [International Atomic Energy Agency, Department of Safeguards, Division of Operations A, Vienna (Austria)

1999-12-31

The basic purpose of the IAEA safeguards system is `timely detection of diversion of significant quantities of nuclear material`. Safeguards implementation is regulated by the IAEA Statute and individual safeguards agreements. The IAEA Inspectorate and its scope are described together with the technical objectives and the concept of verification. Effective implementation of safeguards requires cooperation between the IAEA and the state concerned. To this end, agreements require that the State should establish and maintain a system of accounting for and control of nuclear material subject to safeguards. The IAEA safeguards system has demonstrated a flexibility capable of responding to the verification demands of Member States. Is is capable of safeguarding nuclear materials, facilities, equipment and non-nuclear material. The IAEA is in the process of strengthening safeguards in its verification of declared activities

Review and evaluation of the Nuclear Materials Management and Safeguards System (NMMSS). Volume 1. Comparison of DOE nuclear materials information system requirements with NMMSS capabilities and recommendations for NMMSS improvements

International Nuclear Information System (INIS)

1984-03-01

This report documents the result of a review of the Nuclear Materials Management and Safeguards System (NMMSS), a Department of Energy nuclear materials control and accountability data base and information processing system. This review was performed to determine what data are required from the NMMSS, how it is collected, and how it is used. Based upon the review, NMMSS deficiencies and excess capabilities were identified and a draft set of requirements for the nuclear materials information system that the Office of Safeguards and Security (OSS) should be supporting as well as recommendations for attaining that capability

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

Safeguarding the Plutonium Fuel Cycle

International Nuclear Information System (INIS)

Johnson, S.J.; Lockwood, D.

2013-01-01

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

Development of safeguards approach for the Rokkasho Reprocessing Plant

International Nuclear Information System (INIS)

Johnson, S.J.; Abedin-Zadeh, R.; Pearsall, C.; Chesnay, B.; Creusot, C.; Ehinger, M.; Kuhn, E.; Robson, N.; Higuchi, H.; Takeda, S.; Fujimaki, K.; Ai, H.; Uehara, S.; Amano, H.; Hoshi, K.

2001-01-01

Full text: The Rokkasho Reprocessing Plant (RRP), which is currently undergoing construction and commissioning by the Japan Nuclear Fuels Limited (JNFL), is scheduled to begin active operations in 2005. The planned operating capacity is 800 tonnes of spent fuel per year containing approximately 8 tonnes of plutonium. The International Atomic Energy Agency (IAEA) and the Japan safeguards authorities are working with JNFL to develop a Safeguards Approach that is both effective and efficient. In order to accomplish this goal, a number of advanced concepts are being introduced and many currently applied safeguards measures are being enhanced. These new and improved techniques and procedures will provide for more sensitive and reliable verification of nuclear material and facility operations while reducing the required inspection effort. The Safeguards Approach incorporates systematic Design Information Examination and Verification (DIE/DIV) during all phases of construction, commissioning and operation. It incorporates installed, unattended radiation and solution measurement and monitoring systems along with a number of inspector attended measurement systems. While many of the measurement systems will be independent-inspector controlled, others will require authentication of a split signal from operator controlled systems. The independent and/or authenticated data from these systems will be transmitted over a network to a central inspector center for evaluation. Near-Real-Time-Accountancy (NRTA) will be used for short period sequential analysis of the operator and inspector data which, when combined with Solution Monitoring data, will provide higher assurance in the verification of nuclear material for timeliness and of the operational status of the facility. Samples will be taken using a facility installed, but IAEA authenticated, automatic sampling system and will then be transferred to a jointly used IAEA-JSGO On-Site Laboratory (OSL). This paper provides an

Annual report of the Director of Safeguards 1988-1989

International Nuclear Information System (INIS)

1989-01-01

The Australian Safeguards Office (ASO) operates Australia's state system of accounting for and control of nuclear material. It also contributes to the IAEA safeguards network, in support of the Australian Government's committment to the international nuclear non-proliferation regime. Activities carried out during the year ended 30 June 1989 in each of these areas are reviewed. It is reported that 54 export shipments of uranium ore concentrates containing 5061 tonnes of uranium oxide were made by Australia's three producers and that no unreconcilied differences in quantities of Australian obligated nuclear material, wherever situated, or nuclear material within Australia, regardless of origin, as at 30 June 1989. The report also includes copies of IAEA's statements related to the verification inspections pursuant to the requirements of the Non-Proliferation Treaty Safeguards Agreement

An Introduction to Nuclear Non-Proliferation and Safeguards

International Nuclear Information System (INIS)

Haakansson, Ane; Jonter, Thomas

2007-06-01

The purpose of this project was to compile a course material that covers how the nuclear safeguards system has emerged and how it works today. The produced compendium is directed to both university students and people concerned by safeguards from the industry. The primary aim of the first part of this paper is to describe the historical development of this global non-proliferation system and its central tasks. A second purpose is to discuss the advantages and disadvantages of its current design in order to answer the following question: Can we today say that we have a functioning global non-proliferation system? Does it require further strengthening, and, if so, how can this be achieved? In the second section we review the verification regime within nuclear safeguards, i. e. describe the methods and techniques that are available to reassure the world community that concluded treaties are adhered to

An Introduction to Nuclear Non-Proliferation and Safeguards

Energy Technology Data Exchange (ETDEWEB)

Haakansson, Ane; Jonter, Thomas

2007-06-15

The purpose of this project was to compile a course material that covers how the nuclear safeguards system has emerged and how it works today. The produced compendium is directed to both university students and people concerned by safeguards from the industry. The primary aim of the first part of this paper is to describe the historical development of this global non-proliferation system and its central tasks. A second purpose is to discuss the advantages and disadvantages of its current design in order to answer the following question: Can we today say that we have a functioning global non-proliferation system? Does it require further strengthening, and, if so, how can this be achieved? In the second section we review the verification regime within nuclear safeguards, i. e. describe the methods and techniques that are available to reassure the world community that concluded treaties are adhered to

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

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

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

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

Developing a Signature Based Safeguards Approach for the Electrorefiner and Salt Cleanup Unit Operations in Pyroprocessing Facilities

Energy Technology Data Exchange (ETDEWEB)

Murphy, Chantell Lynne-Marie [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-01-27

Traditional nuclear materials accounting does not work well for safeguards when applied to pyroprocessing. Alternate methods such as Signature Based Safeguards (SBS) are being investigated. The goal of SBS is real-time/near-real-time detection of anomalous events in the pyroprocessing facility as they could indicate loss of special nuclear material. In high-throughput reprocessing facilities, metric tons of separated material are processed that must be accounted for. Even with very low uncertainties of accountancy measurements (<0.1%) the uncertainty of the material balances is still greater than the desired level. Novel contributions of this work are as follows: (1) significant enhancement of SBS development for the salt cleanup process by creating a new gas sparging process model, selecting sensors to monitor normal operation, identifying safeguards-significant off-normal scenarios, and simulating those off-normal events and generating sensor output; (2) further enhancement of SBS development for the electrorefiner by simulating off-normal events caused by changes in salt concentration and identifying which conditions lead to Pu and Cm not tracking throughout the rest of the system; and (3) new contribution in applying statistical techniques to analyze the signatures gained from these two models to help draw real-time conclusions on anomalous events.

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

Preparing the 1993--94 Safeguards Implementation Support Programme for IAEA

International Nuclear Information System (INIS)

Green, L.

1993-01-01

The 1993-94 Safeguards Implementation Support (IS) Program describes the Department of Safeguards' program of implementation support for the coming two years. The main body of the document describes the IS program for IAEA. A detailed description of the individual IS needs for 1993-1994 is contained in an annex that specifies the nee, assigns priorities and lists tasks and activities underway to address the need. Other annexes address policy and procedures for program planning and management, current Member State Support Programs (MSSP) tasks, and identification of MSSP resources required for implementation of developed technologies that could be provided. The primary responsibility for supporting the implementation of safeguards technology is with the support divisions of the Department of Safeguards. However, in this time of limited resources it is essential that, where possible, the Department receives assistance from MSSPs that have the needed resources. This document should serve as a guide for IAEA, in planning implementation support activities and for identifying tasks for MSSPs wishing to provide assistance

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)

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)

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

International Nuclear Information System (INIS)

Metcalf, Richard; Bean, Robert

2009-01-01

The International Atomic Energy Agency (IAEA) implements nuclear safeguards and verifies countries are compliant with their international nuclear safeguards agreements. One of the key provisions in the safeguards agreement is the requirement that the country provide nuclear facility design and operating information to the IAEA relevant to safeguarding the facility, and at a very early stage. , This provides the opportunity for the IAEA to verify the safeguards-relevant features of the facility and to periodically ensure that those features have not changed. The national authorities (State System of Accounting for and Control of Nuclear Material - SSAC) provide the design information for all facilities within a country to the IAEA. The design information is conveyed using the IAEA's Design Information Questionnaire (DIQ) and specifies: (1) Identification of the facility's general character, purpose, capacity, and location; (2) Description of the facility's layout and nuclear material form, location, and flow; (3) Description of the features relating to nuclear material accounting, containment, and surveillance; and (4) Description of existing and proposed procedures for nuclear material accounting and control, with identification of nuclear material balance areas. The DIQ is updated as required by written addendum. IAEA safeguards inspectors examine and verify this information in design information examination (DIE) and design information verification (DIV) activities to confirm that the facility has been constructed or is being operated as declared by the facility operator and national authorities, and to develop a suitable safeguards approach. Under the Next Generation Safeguards Initiative (NGSI), the National Nuclear Security Administrations (NNSA) Office of Non-Proliferation and International Security identified the need for more effective and efficient verification of design information by the IAEA for improving international safeguards in the future

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.

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).

Implementing The Safeguards-By-Design Process

International Nuclear Information System (INIS)

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

2010-01-01

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

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.

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

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

Safeguards technology research and development at CIAE

International Nuclear Information System (INIS)

Yang Qun

2001-01-01

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

National safeguards system operations at a bulk-handling facility

International Nuclear Information System (INIS)

Anon.

1981-01-01

The presentation centers on the State System of Accounting and Control (SSAC) for bulk-handling facilities in the licenses sector of the US nuclear community. Details of those material control and accounting measures dealing with the national safeguards program are discussed in Session 6a. The concept and role of the Fundamental Nuclear Material Control (FNMC) Plan are discussed with the participants. In Session 6b, the lecture focusses on the international safeguards program of the US SSAC. The relationship of the national and international requirements is discussed as they relate to the IAEA INFCIRC/153 document. The purpose of this session is to enable participants to: (1) understand the basic MC and A elements in an SSAC; (2) understand which MC and A elements serve the country's national interests and those that serve IAEA safeguards

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 for reprocessing and enrichment plants

International Nuclear Information System (INIS)

1977-01-01

Agency safeguards are entering a new phase with the coming under active safeguards for the first time of reprocessing plants in several regions of the world. This is taking place at a time when not only the safeguards aspect itself is coming under international scrutiny, but also at a time when the necessity of reprocessing plants is being called into question. Attracting less attention at the moment, but potentially of equal significance, are the enrichment plants that soon will be coming under Agency safeguards. It is not unreasonable in view of the present controversies to ask what is the significance of these reprocessing and enrichment plants, what are the problems concerning safeguards that appear to have given rise to the controversies, and how these problems are to be solved. The question of significance is an easy one to answer. The output of these plants is material which some people consider can be used directly for military purposes, whereas the output from other plants, for instance, reactors, would require long and extensive processing before it could be used for military purposes. Like most short answers, this one is an over-simplification which requires some elaboration to make it strictly accurate. For example, the material output of a power reactor is in the form of irradiate assemblies containing plutonium which is potentially of military use if the irradiation had been within a certain range. However, to utilize this plutonium under clandestine conditions, the highly radioactive material would have to be secretly transported to a reprocessing plant and there would have to be simultaneous falsification of the reactor material accounts and the plant records. Such falsification would be difficult to conceal. The total time required to obtain usable plutonium would be many months. Diversion of material from a uranium fabrication plant making fuel for power reactors would be easier physically but strategically it would be of little value. The

Safeguards Implementation Guide for States with Small Quantities Protocols

International Nuclear Information System (INIS)

2013-01-01

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

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

Safeguards systems concepts for nuclear material transportation. Final report

International Nuclear Information System (INIS)

Baldonado, O.C.; Kevany, M.; Rodney, D.; Pitts, D.; Mazur, M.

1977-09-01

The report describes the development of system concepts for the safeguarding of special strategic nuclear materials (SNM) against malevolent adversary action during the interfacility transport of the SNM. The methodology used includes techniques for defining, classifying, and analyzing adversary action sequences; defining safeguards system components; assessing the vulnerability of various safeguards systems and their component parts to the potential adversary action sequences, and conceptualizing system design requirements. The method of analysis is based primarily on a comparison of adversary actions with safeguards measures, to estimate vulnerability. Because of the paucity of the data available for assessing vulnerability, the Delphi approach was used to generate data: values were estimated in a structured exercise by a panel of experts in the safeguards and terrorist fields. It is concluded that the probability of successful attack against a truck/escort convoy manned by well-trained, well-armed personnel is low enough to discourage all but the strongest adversaries. Secrecy of operations and careful screening of personnel are very important. No reliance should be placed on current capabilities of local law enforcement agencies. The recommendation of the study is the use of road transport in the near future and air transport at a later time when the number of shipments reaches a level to justify it, and when present safety problems are resolved

A Critical Element to Successful Implementation Of Future Safeguards Systems

International Nuclear Information System (INIS)

Dickman, Deborah A.

2003-01-01

As we look to the future of nuclear materials management and safeguards systems, it is essential to place significant emphasis on creation of a strong infrastructure to support and sustain modern systems. Traditionally, safeguards infrastructure development has focused on such elements as equipment development, strengthening of the national regulatory base, creation of state-of-the-art accounting and control systems, and procedure development. Less emphasis has been placed on recognition of the 'human element' as a primary component of the necessary infrastructure and the key to successful implementation of new or existing systems. The importance of the human element can be recognized by considering the broad span of influence and control, direction, regulation and implementation of safeguards systems exhibited by a large number of professionals: diplomats, scholars, politicians, facility managers, program directors and technical specialists. These individuals provide the connectivity or 'glue' that binds together a myriad of smaller safeguards program elements and ensures a holistic approach is fostered and maintained. The education and training of our future leaders and experts must receive the highest priority. In addition, this effort must consider factors beyond development of technical capabilities. Given the rapidly evolving world climate since the end of the cold war, our safeguards leaders and experts need education and training that will provide a well-developed understanding of the broader political dimensions of current nonproliferation challenges. They need to learn how to think, rather than what to think. A sustained effort is required to highlight the importance of the human dimension of safeguards and nuclear materials management and how these systems support international nonproliferation efforts. New educational initiatives are needed to better prepare the next generation of leaders and experts. Increased regional and national cooperation in the

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

RADIO FREQUENCY IDENTIFICATION DEVICES: EFFECTIVENESS IN IMPROVING SAFEGUARDS AT GAS-CENTRIFUGE URANIUM-ENRICHMENT PLANTS

International Nuclear Information System (INIS)

JOE, J.

2007-01-01

Recent advances in radio frequency identification devices (RFIDs) have engendered a growing interest among international safeguards experts. Potentially, RFIDs could reduce inspection work, viz. the number of inspections, number of samples, and duration of the visits, and thus improve the efficiency and effectiveness of international safeguards. This study systematically examined the applications of RFIDs for IAEA safeguards at large gas-centrifuge enrichment plants (GCEPs). These analyses are expected to help identify the requirements and desirable properties for RFIDs, to provide insights into which vulnerabilities matter most, and help formulate the required assurance tests. This work, specifically assesses the application of RFIDs for the ''Option 4'' safeguards approach, proposed by Bruce Moran, U. S. Nuclear Regulatory Commission (NRC), for large gas-centrifuge uranium-enrichment plants. The features of ''Option 4'' safeguards include placing RFIDs on all feed, product and tails (F/P/T) cylinders, along with WID readers in all FP/T stations and accountability scales. Other features of Moran's ''Option 4'' are Mailbox declarations, monitoring of load-cell-based weighing systems at the F/P/T stations and accountability scales, and continuous enrichment monitors. Relevant diversion paths were explored to evaluate how RFIDs improve the efficiency and effectiveness of safeguards. Additionally, the analysis addresses the use of RFIDs in conjunction with video monitoring and neutron detectors in a perimeter-monitoring approach to show that RFIDs can help to detect unidentified cylinders

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

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.

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.

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

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

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

International Nuclear Information System (INIS)

Fritzell, Anni

2008-03-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2008-03-15

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

Machine safety: proper safeguarding techniques.

Science.gov (United States)

Martin, K J

1992-06-01

1. OSHA mandates certain safeguarding of machinery to prevent accidents and protect machine operators. OSHA specifies moving parts that must be guarded and sets criteria for the guards. 2. A 1989 OSHA standard for lockout/tagout requires locking the energy source during maintenance, periodically inspecting for power transmission, and training maintenance workers. 3. In an amputation emergency, first aid for cardiopulmonary resuscitation, shock, and bleeding are the first considerations. The amputated part should be wrapped in moist gauze, placed in a sealed plastic bag, and placed in a container of 50% water and 50% ice for transport. 4. The role of the occupational health nurse in machine safety is to conduct worksite analyses to identify proper safeguarding and to communicate deficiencies to appropriate personnel; to train workers in safe work practices and observe compliance in the use of machine guards; to provide care to workers injured by machines; and to reinforce safe work practices among machine operators.

Role of materials accounting in integrated safeguards systems for reprocessing plants

International Nuclear Information System (INIS)

Hakkila, E.A.; Gutmacher, R.G.; Markin, J.T.; Shipley, J.P.; Whitty, W.J.

1981-01-01

Integration of materials accounting and containment/surveillance techniques for international safeguards requires careful examination and definition of suitable inspector activities for verification of operator's materials accounting data. The inspector's verification procedures are designed to protect against data falsification and/or the use of measurement uncertainties to conceal missing material. Materials accounting activities are developed to provide an effective international safeguards system when combined with containment/surveillance activities described in a companion paper

Managing threats from emerging technologies: can safeguards show the way?

International Nuclear Information System (INIS)

Leffer, Teri N.

2014-01-01

The system of international nuclear safeguards implemented by the International Atomic Energy Agency (IAEA) is primarily a means of verification of states’ commitments under various legal instruments, principally the Nuclear Non‑Proliferation Treaty (NPT), to utilize controlled nuclear fission for peaceful purposes only. However, the safeguards system can also be seen as a mechanism through which states acted to reduce the threat posed by a new technology that had a transformative impact on existing national security paradigms when it emerged in the twentieth century. In the twenty‑first century, new technologies with equally profound national security implications are emerging. These include biotechnology and synthetic biology, nano technology, information technology, cognitive science, robotics and artificial intelligence. Throughout its history, the safeguards system has evolved to accommodate new technologies, new undertakings and new threats. Because multiple emerging technologies now constitute potential national security threats, it is appropriate to consider whether and how the lessons and successes of the safeguards system, including its capacity to evolve in response to changing requirements, could be leveraged to mitigate the threat posed by these new technologies. This paper addresses the possibility of re‑imagining safeguards in a way that makes them applicable to a broader range of technology‑based threats without compromising their effectiveness for their original purpose.

Long-term proliferation and safeguards issues in future technologies

International Nuclear Information System (INIS)

Keisch, B.; Auerbach, C.; Fainberg, A.; Fiarman, S.; Fishbone, L.G.; Higinbotham, W.A.; Lemley, J.R.; O'Brien, J.

1986-02-01

The purpose of the task was to assess the effect of potential new technologies, nuclear and non-nuclear, on safeguards needs and non-proliferation policies, and to explore possible solutions to some of the problems envisaged. Eight subdivisions were considered: New Enrichment Technologies; Non-Aqueous Reprocessing Technologies; Fusion; Accelerator-Driven Reactor Systems; New Reactor Types; Heavy Water and Deuterium; Long-Term Storage of Spent Fuel; and Other Future Technologies (Non-Nuclear). For each of these subdivisions, a careful review of the current world-wide effort in the field provided a means of subjectively estimating the viability and qualitative probability of fruition of promising technologies. Technologies for which safeguards and non-proliferation requirements have been thoroughly considered by others were not restudied here (e.g., the Fast Breeder Reactor). The time scale considered was 5 to 40 years for possible initial demonstration although, in some cases, a somewhat optimistic viewpoint was embraced. Conventional nuclear-material safeguards are only part of the overall non-proliferation regime. Other aspects are international agreements, export controls on sensitive technologies, classification of information, intelligence gathering, and diplomatic initiatives. The focus here is on safeguards, export controls, and classification

Long-term proliferation and safeguards issues in future technologies

Energy Technology Data Exchange (ETDEWEB)

Keisch, B.; Auerbach, C.; Fainberg, A.; Fiarman, S.; Fishbone, L.G.; Higinbotham, W.A.; Lemley, J.R.; O' Brien, J.

1986-02-01

The purpose of the task was to assess the effect of potential new technologies, nuclear and non-nuclear, on safeguards needs and non-proliferation policies, and to explore possible solutions to some of the problems envisaged. Eight subdivisions were considered: New Enrichment Technologies; Non-Aqueous Reprocessing Technologies; Fusion; Accelerator-Driven Reactor Systems; New Reactor Types; Heavy Water and Deuterium; Long-Term Storage of Spent Fuel; and Other Future Technologies (Non-Nuclear). For each of these subdivisions, a careful review of the current world-wide effort in the field provided a means of subjectively estimating the viability and qualitative probability of fruition of promising technologies. Technologies for which safeguards and non-proliferation requirements have been thoroughly considered by others were not restudied here (e.g., the Fast Breeder Reactor). The time scale considered was 5 to 40 years for possible initial demonstration although, in some cases, a somewhat optimistic viewpoint was embraced. Conventional nuclear-material safeguards are only part of the overall non-proliferation regime. Other aspects are international agreements, export controls on sensitive technologies, classification of information, intelligence gathering, and diplomatic initiatives. The focus here is on safeguards, export controls, and classification.

ATLAS TDAQ/DCS Event filter : Supervision Requirements

CERN Document Server

Bee, C P; Meessen, C; Qian, Z; Touchard, F; Green, P; Pinfold, J L; Wheeler, S; Negri, A; Scannicchio, D A; Vercesi, V

2002-01-01

The second iteration of the Software Development Process of the ATLAS Event Filter has been launched. A summary of the design phase of the first iteration is given in the introduction. The document gives constraints, use cases, functional and non-functional requirements for the Supervision sub-system of the Event Filter.

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 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)

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)

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

Safeguards techniques and equipment. 2003 ed

International Nuclear Information System (INIS)

2003-01-01

-destructive analysis (NDA) techniques, and compare their findings with the declared figures and the operator's records. The next level of verification has the aim of detecting whether a fraction of a declared amount is missing (partial defect) and may involve the weighing of items and measurements with NDA techniques such as neutron counting or gamma-ray spectrometry. For detecting bias defects, which would arise if small amounts of material were diverted over a protracted length of time, it is necessary to sample some of the items and to apply physical and chemical analysis techniques having the highest possible accuracy, typically less than one per cent. In order to apply these destructive analysis (DA) techniques, the IAEA requires access to laboratories which use such accurate techniques on a routine basis. Containment and surveillance (C/S) techniques, which are complementary to nuclear material accountancy techniques, are applied in order to maintain continuity of the knowledge gained through IAEA verification, by giving assurance that nuclear material follows predetermined routes, that the integrity of its containment remains unimpaired and that the material is accounted for at the correct measurement points. They also lead to savings in the safeguards inspection effort, e.g. by reducing the frequency of accountancy verification. A variety of C/S techniques are used, primarily optical surveillance and sealing. In remote monitoring, the unattended equipment transmits the data off-site. For unattended and remote monitoring, additional criteria must be met, including high reliability and authentication of the data source. Data communication costs have dropped dramatically in recent years. Data security is an important feature of unattended and remote monitoring systems. Environmental sampling, which allows detection of minute traces of nuclear material, was added to the IAEA's verification measures in the early 1990s as a powerful tool for detecting indications of undeclared

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

Energy Technology Data Exchange (ETDEWEB)

Richard Metcalf; Robert Bean

2009-10-01

Executive Summary The International Atomic Energy Agency (IAEA) implements nuclear safeguards and verifies countries are compliant with their international nuclear safeguards agreements. One of the key provisions in the safeguards agreement is the requirement that the country provide nuclear facility design and operating information to the IAEA relevant to safeguarding the facility, and at a very early stage. , This provides the opportunity for the IAEA to verify the safeguards-relevant features of the facility and to periodically ensure that those features have not changed. The national authorities (State System of Accounting for and Control of Nuclear Material - SSAC) provide the design information for all facilities within a country to the IAEA. The design information is conveyed using the IAEA’s Design Information Questionnaire (DIQ) and specifies: (1) Identification of the facility’s general character, purpose, capacity, and location; (2) Description of the facility’s layout and nuclear material form, location, and flow; (3) Description of the features relating to nuclear material accounting, containment, and surveillance; and (4) Description of existing and proposed procedures for nuclear material accounting and control, with identification of nuclear material balance areas. The DIQ is updated as required by written addendum. IAEA safeguards inspectors examine and verify this information in design information examination (DIE) and design information verification (DIV) activities to confirm that the facility has been constructed or is being operated as declared by the facility operator and national authorities, and to develop a suitable safeguards approach. Under the Next Generation Safeguards Initiative (NGSI), the National Nuclear Security Administrations (NNSA) Office of Non-Proliferation and International Security identified the need for more effective and efficient verification of design information by the IAEA for improving international safeguards

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

Energy Technology Data Exchange (ETDEWEB)

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

2016-07-24

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

Australian Safeguards and Non-Proliferation Office and the Chemical Weapons Convention Annual Report 1999-2000

International Nuclear Information System (INIS)

2000-01-01

The Director General, Australian Safeguards and Non-Proliferation Office (ASNO), combines the statutory office of Director of Safeguards with that of Director, Chemical Weapons Convention Office (CWCO). The Director General also performs the functions of the Director, Australian Comprehensive Test-Ban Office (ACTBO) on an informal basis, as the relevant legislation has not yet come into effect. Throughout the year, ASNO made a substantial contribution to the development of strengthened IAEA safeguards and the integration of strengthened safeguards with the established (classical) safeguards system. ASNO is working closely with the IAEA to develop the procedures and methods required to effectively implement the IAEA's authority and responsibilities as the Additional Protocol enters general application, as well as the specific arrangements which will apply in Australia. In the latter context, ASNO offers the IAEA a safeguards-friendly environment, together with constructive critique, to assist in the development and testing of new techniques. This work is important in ensuring the effective implementation of strengthened safeguards elsewhere. Substantial progress were made on several new bilateral nuclear safeguards agreements. An agreement with the US covering transfer of the Silex laser enrichment technology came into force, and ASNO is now working with US authorities to develop the detailed administrative arrangements required to give effect to this agreement. Also concluded during the year was an agreement with New Zealand covering transfers of uranium for non-nuclear use (as a colouring agent in glass manufacture). ASNO was also working closely with ANSTO to ensure that nuclear material accountancy and control at Lucas Heights accords with best international practice, particularly having regard to the requirements of the IAEA under integrated safeguards. Excellent professional relationship were maintained with the OPCW and counterpart national authorities

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

SGNucDat. Safeguards nuclear data for windows. Summary documentation

International Nuclear Information System (INIS)

Lemmel, H.D.; Schwerer, O.

1996-01-01

SGNucDat is a PC code displaying recommended values of nuclear data that are required for nuclear materials analyses by IAEA safeguards. Diskette and report available from the IAEA Nuclear Data Section, costfree upon request. (author)

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)

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)

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 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)

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

Safety, Security and Safeguards (3S) Culture

International Nuclear Information System (INIS)

Mladineo, S.V.; Frazar, S.

2013-01-01

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

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

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

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

Implementation of safeguards in Spanish NPPs: advantages of cooperation and coordination

International Nuclear Information System (INIS)

Estrampes Blanch, J.; Recio Santamaria, M.

2007-01-01

In 2002 the Spanish Ministry of Industry, Tourism and Commerce (MITYC) informed the operators of the soon entry into force of the Additional Protocol (AP) to the Safeguards Agreement, once its ratification by the Member States of the EU were completed and the Community and national legislations were adapted to the new requirements. The Spanish association for the electrical industry (UNESA) responded to that announcement setting up the UNESA's Safeguards Working Group (USWG), made up of staff of the NPPs in charge of nuclear material accountancy. The USWG was mandated to ensure coordinated implementation of the new safeguards obligation of the Additional Protocol in close cooperation with the Ministry of Industry, Tourism and Commerce (MITYC), Spanish authority for safeguards implementation follow up. Although the group was initially meant only for NPPs, later on representatives of other main nuclear facilities (i.e. ENUSA's fuel fabrication facility, the national rad waste company ENRESA, and CIEMAT national research centre) have been also participating in the group's meeting and activities when general discussion points on the entry into force of the AP were dealt with. From 2003 on, the USWG has met periodically with the aim of exchanging experiences in the field of safeguards implementation and jointly dealing with changes to EURATOM and IAEA safeguards systems lately introduced to reinforce their effectiveness and efficiency in response to the challenges posed to the international community by the recent discovery of undeclared nuclear programmes. Along the operation of the USWG, presence of Spanish nuclear industry representatives in international for a dealing with safeguards has remarkably grown up. Moreover, representatives of the USWG have also maintained an active participation in the ESARDA working groups on integrated safeguards (ISWG) and nuclear material accountancy and audit focus group (NMAC-AF)

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

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

Potential nuclear material safeguards applied to the Department of Energy's Civilian Radioactive Waste Management System

International Nuclear Information System (INIS)

Danker, W.J.; Floyd, W.

1993-01-01

The Office of Civilian Radioactive Waste Management (OCRWM) within the U.S. Department of Energy is charged with the responsibility of safe and efficient disposal of this Nation's civilian high-level radioactive waste and spent fuel. Part of this responsibility includes providing for the application of both domestic and international safeguards on nuclear material at facilities of the Civilian Waste Management System. While detailed safeguards requirements for these disposal facilities have yet to be established, once established, they could impact facility design. Accordingly, OCRWM has participated in efforts to develop safeguards approaches for geologic repositories and will continue to participate actively with the Nuclear Regulatory Commission (NRC), International Atomic Energy Agency (IAEA), as well as other Department of Energy (DOE) Offices in efforts to resolve safeguards issues related to spent fuel disposal, to minimize any potential design impacts and to support effective nuclear material safeguards. The following paper discusses current plants and issues related to the application of safeguards to the Civilian Radioactive Waste Management System (CRWMS)

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

Redefining interrelationship between nuclear safety, nuclear security and safeguards

International Nuclear Information System (INIS)

Irie, Kazutomo

2011-01-01

Since the beginning of this century, the so-called 3Ss (Nuclear Safety, Nuclear Security and Safeguards) have become major regulatory areas for peaceful uses of nuclear energy. The importance of the 3Ss is now emphasized to countries which are newly introducing nuclear power generation. However, as role models for those newcomers, existing nuclear power countries are also required to strengthen their regulatory infrastructure for the 3Ss. In order to rationalize the allocation of regulatory resources, interrelationship of the 3Ss should be investigated. From the viewpoint of the number of the parties concerned in regulation, nuclear security is peculiar with having 'aggressors' as the third party. From the viewpoint of final goal of regulation, nuclear security in general and safeguards share the goal of preventing non-peaceful uses of nuclear energy, though the goal of anti-sabotage within nuclear security is rather similar to nuclear safety. As often recognized, safeguards are representative of various policy tools for nuclear non-proliferation. Strictly speaking, it is not safeguards as a policy tool but nuclear non-proliferation as a policy purpose that should be parallel to other policy purposes (nuclear safety and nuclear security). That suggests 'SSN' which stands for Safety, Security and Non-proliferation is a better abbreviation rather than 3Ss. Safeguards as a policy tool should be enumerated along with nuclear safety regulation, nuclear security measures and trade controls on nuclear-related items. Trade controls have been playing an important role for nuclear non-proliferation. These policy tools can be called 'SSST' in which Trade controls are also emphasized along with Safety regulation, Security measures and Safeguards. Recently, it becomes quite difficult to clearly demarcate these policy tools. As nuclear security concept is expanding, the denotation of nuclear security measures is also expanding. Nuclear security measures are more and more

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

Designing a safeguards approach for the transfer and storage of used fuel

International Nuclear Information System (INIS)

Benjamin, Robert; Truong, Q.S. Bob; Keeffe, Richard; Whiting, Neville; Green, Brian

2001-01-01

Full text: To provide needed space in the bays for continued CANDU reactor discharges, used fuel must be moved from the bays to dry storage facilities, which are built on site. Over the next decades, used fuel in the bays in Canada will be loaded into containers or transfer flasks and moved to the dry storage facilities. The IAEA currently verifies the transfer of used fuel to dry storage at the Point Lepreau and Gentilly and Pickering CANDU reactor stations. When the Bruce Used Fuel Dry Storage Facility starts operating in 2002 followed by the Darlington Used Fuel Dry Storage Facility in 2007-2009 increased Agency safeguards resources will be required. Safeguarding these new facilities and the flow of fuel to them would place additional demand on IAEA resources if the current approach, which relies heavily upon inspectors being present at the facility, were used. In a continuous search for more efficient approaches, the IAEA, the Canadian Nuclear Safety Commission, and the facility operators are working together to develop a safeguards scheme that depends less upon inspectors and more upon instruments, operator activity and remote monitoring. This paper describes the current approach to safeguarding used fuel in transit and in storage at the Pickering site and how that approach might be applied to the Bruce site. Alternative approaches are also discussed and their application to existing and future used fuel dry storage facilities is considered. Safeguards approaches under existing Safeguards Criteria are compared with approaches that might be possible under a safeguards regime strengthened by the Additional Protocol, and with approaches optimised under Integrated Safeguards. The technologies being considered to safeguard used fuel include position tracking using Global Positioning System (GPS), Geospatial Information System (GIS), radio frequency techniques, electronic seals, operator activity and remote surveillance and monitoring. (author)

Smart unattended systems for plutonium safeguards

International Nuclear Information System (INIS)

Menlove, H.O.; Abhold, M.; Eccleston, G.; Puckett, J.M.

1996-01-01

Large automated facilities for fabricating plutonium fuel present both difficulties and challenges for improved accounting of nuclear materials. The traditional methods of sample measurements, requiring the transfer of the sample from the production line to the assay measurement station, are not possible in automated facilities. The robotics used for automation require special containers for nuclear material that cannot be easily removed from the production line. Safety and radiation protection considerations also require that the assay instrumentation be installed in the fuel production lines because, in general, personnel cannot be in the fuel-handling area with nuclear material during operations. Such operational constraints are common in many of the modern facilities that have been designed for fabricating and processing plutonium fuel. A bilateral safeguards agreement between the US Department of Energy (DOE) and Power Reactor and Nuclear Fuel Development Corporation (PNC) in Japan was signed to develop and implement nondestructive assay (NDA) systems to provide continuous safeguards measurements for material accountancy in the robot-automated Plutonium Fuel Fabrication Facility (PFFF). The PFFF assay systems were required to operate in unattended mode with a size and fuel mass capability to match the robotics fuel manipulators. Unattended assay systems reduce the requirement for inspector's oversight of measurement operations, reduce the inspector's workload, and improve inspection efficiencies. In addition, unattended measurements become essential when facility constraints limit the access of inspectors to the operations area during material processing. Authentication techniques were incorporated into the NDA systems so that data obtained from unattended assays could be used by independent inspectors such as the IAEA

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

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.)

The effect of safeguards on the contractual relations of nuclear suppliers

International Nuclear Information System (INIS)

MacIsaac, J.F.D.

1976-01-01

Canada applies a safeguards system aimed to ensure that nuclear materials and equipment are not diverted from their peaceful uses. These control requirements have a direct influence on the conditions of export contracts concluded by Canadian suppliers of nuclear materials or equipment. In particular if the buyer does not comply with the safeguards clauses, it may not be possible for the Canadian supplier to fulfill the contract. This possibility is covered by the force majeure clauses. (N.E.A.) [fr

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)

The Connection between the Areas of Safeguards and Physical Protection and Record and Memory Keeping

International Nuclear Information System (INIS)

Ormai, Peter; )

2012-01-01

Safeguards are concerned with nuclear - especially fissile - materials and associated technology. In general, nuclear safeguards exist on different levels, each with different motivations (the facility operator, national authority, international authority). Safeguards basically comes down to accountancy on fissile material (mainly U an Pu), which seeks to verify the 'material balance'. For international nuclear safeguards, accountancy assures that nuclear materials are present and used as intended. International safeguards are called for by treaties and other agreements between parties. EURATOM and IAEA are the main actors. Implementing safeguards for geological disposal is considered a big challenge as it is a new area. Although the complementarity between safeguards and general RK and M preservation was pointed out, there are also substantial differences. With regard to complementarity, it was mentioned that the challenges for preserving of IAEA safeguards relevant information and documentation are the same as that of other long term archiving. An effective application of safeguards shall assure continuity-of-knowledge about the nuclear material in the repository. A variety of technical tools enables safeguards to provide accountancy and continuity of knowledge of nuclear materials.. On the other hand it was mentioned that safeguards are only interested in fissile materials, so e.g. not really in intermediate level waste. Moreover, safeguards records keeping is a State, not a waste agency responsibility. Some more fundamental, challenging differences were also pointed out. For instance, although the record-keeping requirements for retrievability and safeguards might be considered to be complementary, their aims are in fact opposite. Safeguards can only be abandoned in case of practical irretrievability. Whether this is possible remains a question mark. In any case spent fuel will never be regarded as 'waste' by the safeguards community. Another issue is the

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

One of the IAEA's statutory objectives is to seek to accelerate and enlarge the contribution of nuclear energy to peace, health and prosperity throughout the world. One way the IAEA works to achieve this objective is through the publication of technical series that can provide guidance to Member States. These series include the IAEA Services Series, the IAEA Safety Standard Series, the IAEA Nuclear Security Series and the IAEA Nuclear Energy Series. The Nuclear Energy Series is comprised of publications designed to encourage and assist research and development on, and practical application of, nuclear energy for peaceful purposes. This includes guidance to be used by owners and operators of utilities, academia, vendors and government officials. The IAEA has chosen the Nuclear Energy Series to publish guidance for States regarding the consideration of safeguards in nuclear facility design and construction. Historically, safeguards were often applied after a facility was designed or maybe even after it was built. However, many in the design and construction community would prefer to include consideration of these requirements from the conceptual design phase in order to reduce the need for retro-fits and modifications. One can then also take advantage of possible synergies between safeguards, security, safety and environmental protection and reduce the project risk against cost increments and schedule slippage. The IAEA is responding to this interest with a suite of publications in the IAEA Nuclear Energy Series, developed with the assistance of a number of Member State Support Programmes through a joint support programme task: · International Safeguards in Nuclear Facility Design and Construction (NP-T-2.8, 2013), · International Safeguards in the Design of Nuclear Reactors (NP-T-2.9, 2014), · International Safeguards in the Design of Spent Fuel Management (NF-T-3.1, tbd), · International Safeguards in the Design of Fuel Fabrication Plants (NF-T-4.7, tbd

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

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

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

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

Behavior of 241Am in fast reactor systems - a safeguards perspective

International Nuclear Information System (INIS)

Beddingfield, David H.; Lafleur, Adrienne M.

2009-01-01

Advanced fuel-cycle developments around the world currently under development are exploring the possibility of disposing of 241 Am from spent fuel recycle processes by burning this material in fast reactors. For safeguards practitioners, this approach could potentially complicate both fresh- and spent-fuel safeguards measurements. The increased (α,n) production in oxide fuels from the 241 Am increases the uncertainty in coincidence assay of Pu in MOX assemblies and will require additional information to make use of totals-based neutron assay of these assemblies. We have studied the behavior of 241 Am-bearing MOX fuel in the fast reactor system and the effect on neutron and gamma-ray source-terms for safeguards measurements. In this paper, we will present the results of simulations of the behavior of 241 Am in a fast breeder reactor system. Because of the increased use of MOX fuel in thermal reactors and advances in fuel-cycle designs aimed at americium disposal in fast reactors, we have undertaken a brief study of the behavior of americium in these systems to better understand the safeguards impacts of these new approaches. In this paper we will examine the behavior of 241 Am in a variety of nuclear systems to provide insight into the safeguards implications of proposed Am disposition schemes.

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

10 CFR 76.119 - Security facility approval and safeguarding of National Security Information and Restricted Data.

Science.gov (United States)

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Security facility approval and safeguarding of National Security Information and Restricted Data. 76.119 Section 76.119 Energy NUCLEAR REGULATORY COMMISSION... approval and safeguarding of National Security Information and Restricted Data. The requirements for...

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 Licensing Aspects of a Future Gen IV Test Facility - a Case Study

International Nuclear Information System (INIS)

Lindell, M. Aberg; Grape, S.; Hakansson, A.; Svaerd, S. Jacobsson

2010-01-01

The scope of this study covers safeguards licensing aspects of a possible future Gen IV demonstration facility. As a basis for the investigation, the facility was assumed to be located in Sweden, comprising a lead-cooled fast reactor and a reprocessing plant with fuel fabrication. The aim has been to identify safeguards requirements that may be set by the IAEA and the Swedish Radiation Safety Authority, and also to suggest how the safeguards system could be implemented in practice. The changed usage and handling of nuclear fuel, as compared to that of today, has been examined in order to determine how today's safeguards measures can be modified and extended to meet the needs of the demonstration facility. This work is part of GENIUS, the Swedish Gen IV research and development programme, which emphasizes lead-cooled fast reactors. (author)

Overview of safeguards aspects related to MOX fuel

International Nuclear Information System (INIS)

Heinonen, O.J.; Murakami, K.; Shea, T.

2000-01-01

Recent developments in the light of the IAEA verification requirements for MOX fuel at reactors and bulk handling facilities are discussed. Impact of the Additional Protocol and Integrated Safeguards System is briefly addressed. Agency's work undertaken with regard to the nuclear arms control and reduction is presented. (author)

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

International Nuclear Information System (INIS)

Anttila, M.

2000-08-01

Finland under the national and international safeguards is very limited, the main objects under control being four light-water reactors with a once-through uranium based fuel cycle. On the other hand, the national safeguards system is strong and competent. Therefore, Finland should be able to fulfill the provisions of the Additional Protocol fast and well. Also the state-level evaluation of Finland by the IAEA can be assumed to be quite straightforward. An IS system suitable to the Finnish conditions would put an end to the interim routine inspections and to the use of permanent camera surveillance. On the other hand, the IAEA could carry out one unannounced or short-notice inspection per year in Finland. The Agency would also get continuously up-to-date information of all nuclear activities in the country. The Finnish SSAC is assumed to be maintained and further developed also in the future. The national safeguards inspections and measurements by Finnish Radiation and Nuclear Safety Authority (STUK) would be continued. The implementation of the provisions of the Additional Protocol and the application of the IS system in Finland requires good cooperation, mutual trust and division of work between four actors of the play: the operators of the nuclear facilities, STUK, Euratom and the IAEA. Each of them shall have the well-specified roles and functional responsibilities. The international safeguards agencies should utilise the national resources more effectively than before. (orig.)

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

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.

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

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)

Nondestructive Neutron And Gamma-Ray Technologies Applied To GNEP And Safeguards

International Nuclear Information System (INIS)

Dougan, A D; Snyderman, N; Ham, Y; Nakae, L; Dietrich, D; Kerr, P; Wang, T; Stoeffl, W; Choi, J S

2007-01-01

In recent years, LLNL has developed methods for diagnosing significant quantities of special nuclear material (SNM). Homeland security problems have recently focused our attention on detection of shielded highly enriched uranium (HEU), which is a weak signal problem. Current and advanced safeguards applications will require working in the opposite extreme of strong but buried signals. We will review some of the technologies that have been developed at LLNL for homeland security applications and discuss how they might be used in support of international safeguards

Evaluating safeguards effectiveness against protracted theft of special nuclear material by insiders

International Nuclear Information System (INIS)

Al-Ayat, R.; Sicherman, A.

1991-01-01

The new draft DOE Material Control and Accountability Order 5633.3 requires that facilities handling special nuclear material (SNM) evaluate their effectiveness against provided theft of SNMProtracted theft means repeated thefts of small quantities of material to accumulate a goal quanfity. To evaluate the safeguards effectiveness against pro thefts, one must addresses several issues: (1) defining relevant time frames for various threat scenarios and delayed detection safeguards: (2) identifying which safeguards come into play more than once because of repeated adversary actions or because of periodic occurrence during the theft time frame (e.g., daily administrative check on presence of material): (3) considering whether the second and subsequent applications of safeguards are different in effectiveness from the first; (4)synthesizing how physical security, material control, and material accountability safeguards combine to provide protection against protracted theft scenarios. In this paper we discuss these issues and describe how we are augmenting the Analytic System and Software for Evaluating Safeguards and Security (ASSESS) to provide the user with a tool for evaluating effectiveness against protracted theft. Currently, the Insider module of ASSESS focuses on evaluating the ''timely'' detection of abrupt theft attempts by various types of single nonviolent insiders. In this paper we describe the approach we're implementing to augment ASSESS to handle various cases of protracted theft attempts

Safeguards and Security by Design (SSBD) for Small Modular Reactors (SMRs) through a Common Global Approach

Energy Technology Data Exchange (ETDEWEB)

Badwan, Faris M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Demuth, Scott Francis [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Miller, Michael Conrad [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Pshakin, Gennady [Obninsk Institute of Physics and Power Engineering (Russian Federation)

2015-02-23

Small Modular Reactors (SMR) with power levels significantly less than the currently standard 1000 to 1600-MWe reactors have been proposed as a potential game changer for future nuclear power. SMRs may offer a simpler, more standardized, and safer modular design by using factory built and easily transportable components. Additionally, SMRs may be more easily built and operated in isolated locations, and may require smaller initial capital investment and shorter construction times. Because many SMRs designs are still conceptual and consequently not yet fixed, designers have a unique opportunity to incorporate updated design basis threats, emergency preparedness requirements, and then fully integrate safety, physical security, and safeguards/material control and accounting (MC&A) designs. Integrating safety, physical security, and safeguards is often referred to as integrating the 3Ss, and early consideration of safeguards and security in the design is often referred to as safeguards and security by design (SSBD). This paper describes U.S./Russian collaborative efforts toward developing an internationally accepted common approach for implementing SSBD/3Ss for SMRs based upon domestic requirements, and international guidance and requirements. These collaborative efforts originated with the Nuclear Energy and Nuclear Security working group established under the U.S.-Russia Bilateral Presidential Commission during the 2009 Presidential Summit. Initial efforts have focused on review of U.S. and Russian domestic requirements for Security and MC&A, IAEA guidance for security and MC&A, and IAEA requirements for international safeguards. Additionally, example SMR design features that can enhance proliferation resistance and physical security have been collected from past work and reported here. The development of a U.S./Russian common approach for SSBD/3Ss should aid the designer of SMRs located anywhere in the world. More specifically, the application of this approach may

Safeguards and Security by Design (SSBD) for Small Modular Reactors (SMRs) through a Common Global Approach

International Nuclear Information System (INIS)

Badwan, Faris M.; Demuth, Scott Francis; Miller, Michael Conrad; Pshakin, Gennady

2015-01-01

Small Modular Reactors (SMR) with power levels significantly less than the currently standard 1000 to 1600-MWe reactors have been proposed as a potential game changer for future nuclear power. SMRs may offer a simpler, more standardized, and safer modular design by using factory built and easily transportable components. Additionally, SMRs may be more easily built and operated in isolated locations, and may require smaller initial capital investment and shorter construction times. Because many SMRs designs are still conceptual and consequently not yet fixed, designers have a unique opportunity to incorporate updated design basis threats, emergency preparedness requirements, and then fully integrate safety, physical security, and safeguards/material control and accounting (MC&A) designs. Integrating safety, physical security, and safeguards is often referred to as integrating the 3Ss, and early consideration of safeguards and security in the design is often referred to as safeguards and security by design (SSBD). This paper describes U.S./Russian collaborative efforts toward developing an internationally accepted common approach for implementing SSBD/3Ss for SMRs based upon domestic requirements, and international guidance and requirements. These collaborative efforts originated with the Nuclear Energy and Nuclear Security working group established under the U.S.-Russia Bilateral Presidential Commission during the 2009 Presidential Summit. Initial efforts have focused on review of U.S. and Russian domestic requirements for Security and MC&A, IAEA guidance for security and MC&A, and IAEA requirements for international safeguards. Additionally, example SMR design features that can enhance proliferation resistance and physical security have been collected from past work and reported here. The development of a U.S./Russian common approach for SSBD/3Ss should aid the designer of SMRs located anywhere in the world. More specifically, the application of this approach may

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 agreement and additional protocol - IAEA instruments for control of nuclear materials distribution and their application in Tajikistan

International Nuclear Information System (INIS)

Nasrulloev, Kh.; Mirsaidov, U.

2010-01-01

Full text: It is known that IAEA plays an important role in facilitation of nuclear non-proliferation as international authority which carries out nuclear inspections. Republic of Tajikistan in 1997 signed nuclear weapon non-proliferation treaty. Then in 2004 Safeguards agreement, additional protocol and small quantity protocol were signed. During 5 years Republic of Tajikistan submits information on its nuclear activity as declarations, foreseen in article 2.3 of Additional protocol to Safeguards agreement. Currently 66 declarations are submitted. Information required in accordance with Safeguards agreement and Additional Protocol is figured on that IAEA could compile more detailed and exact conception about nuclear activity in Tajikistan and it has the following purpose: information will lead to more transparency, and make it possible to IAEA to ensure with high extent of confidence that in the framework of declared program, any unstated nuclear activity is concealed; the more exact and comprehensive information, the rare is questions and discrepancies are originating; required information is the basis for effective planning and IAEA activity realization, related not only with safeguards implementation in regard to declared nuclear material but also ensuring of confidence in absence of undeclared nuclear activity in Tajikistan. IAEA inspection mission consisting of Messrs. N.Lazarev and F. Coillou visited Dushanbe in 2008 for verification of republic’s declarations on account for and control of nuclear materials under Additional protocol and Small quantity protocol, as well as consultations were provided on correct declaration completing and providing information on all nuclear materials. Besides, in 2006, the training course was conducted in Chkalovsk with participation of Commonwealth of Independent States countries on Safeguards agreement and Additional protocol. These visits and events will facilitate to strengthening of weapons of mass destruction non

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

Current Status of J-MOX Safeguards Design and Future Prospects

International Nuclear Information System (INIS)

Sampei, T.; Hiruta, K.; Shimizu, J.; Ikegame, K.

2015-01-01

The construction of JNFL MOX Fuel Fabrication Plant (J-MOX) is proceeding toward active test using uranium and MOX in July 2017, and completion of construction in October 2017. Although the construction schedule is largely impacted by progress of licencing, according to domestic law, JNFL is making every effort to get necessary permission of business licence and authorization of design and construction method as soon as possible. On the other hand, it is desirable that integrated safeguards approach is effective, efficient and consistent with J-MOX facility features. Discussion about the approach is going on among IAEA, Japan Safeguards Office (JSGO) and JNFL, and IAEA is planning to introduce the measures into the approach such as application of Near Real-Time Accountancy with frequent declaration from operator, Containment/Surveillance measures to storages, internal flow verification with 100%, random interim inspection (RII) and so on. RII scheme is intended to increase efficiency without compromising effectiveness and makes interruption of facility operation minimum. Also newly developed and improved safeguards equipment will be employed and it is possible to realize to increase credibility and efficiency of inspection by introduction of unattended/automatic safeguards equipment. Especially IAEA and JSGO share the development of non-destructive assay systems which meet the requirements from both parties. These systems will be jointly utilized at the flow verification, RII and PIV. JNFL will continue to provide enough design information in a timely manner toward early establishment of safeguards approach for J-MOX. Also JNFL will implement the coordination of installation and commissioning of safeguards equipment, and Design Information Verification activities for completion of construction in October 2017

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)