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

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

INL Human Resource Development and the Next-Generation Safeguards Initiative

Energy Technology Data Exchange (ETDEWEB)

Gouveia, Fernando; Metcalf, Richard Royce Madison

2010-07-01

It is the stated goal of the Next Generation Safeguards Initiative (NGSI) to promote the development of a strengthened nuclear safeguards base, one with the potential to advance the secure and peaceful implementation of nuclear energy world-wide. To meet this goal, the initiative, among other things, has sought to develop a revitalized effort to ensure the continued availability of next generation safeguards professionals. Accordingly, this paper serves to outline the human capital building strategies taken by Idaho National Laboratory (INL) in line with the NGSI. Various components are presented in detail, including INL’s efforts directed at university outreach, in particular the laboratory’s summer internship program, along with the development of various innovative training programs and long-term oriented strategies for student professional development. Special highlights include a video training series, developed by INL in cooperation with LLNL and other laboratories, which sought to expose students and entry-level professionals to the concept and practice of international nuclear safeguards.

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

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

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

The International Atomic Energy Agency's safeguards system

International Nuclear Information System (INIS)

Wagner, W.

2000-01-01

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

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

Symposium on international safeguards: Verification and nuclear material security. Book of extended synopses

International Nuclear Information System (INIS)

2001-01-01

The symposium covered the topics related to international safeguards, verification and nuclear materials security, namely: verification and nuclear material security; the NPT regime: progress and promises; the Additional Protocol as an important tool for the strengthening of the safeguards system; the nuclear threat and the nuclear threat initiative. Eighteen sessions dealt with the following subjects: the evolution of IAEA safeguards (including strengthened safeguards, present and future challenges; verification of correctness and completeness of initial declarations; implementation of the Additional Protocol, progress and experience; security of material; nuclear disarmament and ongoing monitoring and verification in Iraq; evolution of IAEA verification in relation to nuclear disarmament); integrated safeguards; physical protection and illicit trafficking; destructive analysis for safeguards; the additional protocol; innovative safeguards approaches; IAEA verification and nuclear disarmament; environmental sampling; safeguards experience; safeguards equipment; panel discussion on development of state systems of accountancy and control; information analysis in the strengthened safeguard system; satellite imagery and remote monitoring; emerging IAEA safeguards issues; verification technology for nuclear disarmament; the IAEA and the future of nuclear verification and security

Symposium on international safeguards: Verification and nuclear material security. Book of extended synopses

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

The symposium covered the topics related to international safeguards, verification and nuclear materials security, namely: verification and nuclear material security; the NPT regime: progress and promises; the Additional Protocol as an important tool for the strengthening of the safeguards system; the nuclear threat and the nuclear threat initiative. Eighteen sessions dealt with the following subjects: the evolution of IAEA safeguards (including strengthened safeguards, present and future challenges; verification of correctness and completeness of initial declarations; implementation of the Additional Protocol, progress and experience; security of material; nuclear disarmament and ongoing monitoring and verification in Iraq; evolution of IAEA verification in relation to nuclear disarmament); integrated safeguards; physical protection and illicit trafficking; destructive analysis for safeguards; the additional protocol; innovative safeguards approaches; IAEA verification and nuclear disarmament; environmental sampling; safeguards experience; safeguards equipment; panel discussion on development of state systems of accountancy and control; information analysis in the strengthened safeguard system; satellite imagery and remote monitoring; emerging IAEA safeguards issues; verification technology for nuclear disarmament; the IAEA and the future of nuclear verification and security.

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)

Symposium on international safeguards: Verification and nuclear material security. Book of extended synopses. Addendum

International Nuclear Information System (INIS)

2001-01-01

The symposium covered the topics related to international safeguards, verification and nuclear materials security, namely: verification and nuclear material security; the NPT regime: progress and promises; the Additional Protocol as an important tool for the strengthening of the safeguards system; the nuclear threat and the nuclear threat initiative. Eighteen sessions dealt with the following subjects: the evolution of IAEA safeguards ( including strengthened safeguards, present and future challenges; verification of correctness and completeness of initial declarations; implementation of the Additional Protocol, progress and experience; security of material; nuclear disarmament and ongoing monitoring and verification in Iraq; evolution of IAEA verification in relation to nuclear disarmament); integrated safeguards; physical protection and illicit trafficking; destructive analysis for safeguards; the additional protocol; innovative safeguards approaches; IAEA verification and nuclear disarmament; environmental sampling; safeguards experience; safeguards equipment; panel discussion on development of state systems of accountancy and control; information analysis in the strengthened safeguard system; satellite imagery and remote monitoring; emerging IAEA safeguards issues; verification technology for nuclear disarmament; the IAEA and the future of nuclear verification and security

International safeguards

International Nuclear Information System (INIS)

Petit, A.

1991-01-01

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

International Nuclear Safeguards Inspection Support Tool (INSIST)

International Nuclear Information System (INIS)

St. Pierre, D.E.; Steinmaus, K.L.; Moon, B.D.

1994-07-01

DOE is committed to providing technologies to the International Atomic Energy Agency (IAEA) to meet escalating monitoring and inspection requirements associated with the Non-Proliferation Treaty (NPT). One example of technology provided to the IAEA is the information management and remote monitoring capabilities being customized for the IAEA by the International Safeguards Division of the Office of Non-Proliferation and National Security. The ongoing Safeguards Information Management Systems (SIMS) program is an interlaboratory effort providing the IAEA with a range of information management capabilities designed to enhance the effectiveness of their nuclear inspection activities. The initial commitment involved the customization of computer capabilities to provide IAEA with the basic capability to geographically organize, store, and retrieve the large quantity of information involved in their nuclear on site inspection activities in Iraq. This initial system, the International Nuclear Safeguards Inspection Support Tool (INSIST), was developed by DOE's Pacific Northwest Laboratory (PNL). To date, two INSIST workstations have been deployed at the IAEA. The first has been used to support the IAEA Action Team in the inspection of Iraqi nuclear facilities since August 1993. A second, and similar, workstation has been deployed to support environmental monitoring under the IAEA 93+2 Programme. Both INSIST workstations geographically integrate analog (video) and digital data to provide an easy to use and effective tool for storing retrieving and displaying multimedia site and facility information including world-wide maps, satellite and aerial imagery, on site photography, live inspection videos, and treaty and inspection textual information. The interactive, UNIX-based workstations have a variety of peripheral devices for information input and output. INSIST software includes commercial-off-the-shelf (COTS) modules and application-specific code developed at PNL

Canada and international safeguards. Verifying nuclear non-proliferation

International Nuclear Information System (INIS)

1990-01-01

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

International safeguards for critical facilities

International Nuclear Information System (INIS)

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

1979-01-01

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

International safeguards

International Nuclear Information System (INIS)

1995-01-01

The system of international safeguards carried out by the IAEA is designed to verify that governments are living up to pledges to use nuclear energy only for peaceful purposes under the NPT (Treaty on the non-proliferation of nuclear weapons) and similar agreements. The film illustrates the range of field inspections and analytical work involved. It also shows how new approaches are helping to strengthen the system

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.

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

Science.gov (United States)

2010-01-01

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

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

Non-proliferation and international safeguards. [Booklet by IAEA

Energy Technology Data Exchange (ETDEWEB)

1978-01-01

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

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

Goals of measurement systems for international safeguards

International Nuclear Information System (INIS)

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

1979-01-01

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

13 CFR 107.506 - Safeguarding Licensee's assets/Internal controls.

Science.gov (United States)

2010-01-01

.../Internal controls. 107.506 Section 107.506 Business Credit and Assistance SMALL BUSINESS ADMINISTRATION... Safeguarding Licensee's assets/Internal controls. You must adopt a plan to safeguard your assets and monitor... your control procedures. ...

Informing the public on technical effectiveness of international safeguards

International Nuclear Information System (INIS)

Hunt, H.M.

1994-01-01

In recent years, public interest regarding IAEA (International Atomic Energy Agency) safeguards effectiveness has partially shifted to detection of undeclared nuclear facilities. Nevertheless, important segments of the public remain vitally interested in whether international safeguards would be able to reliably and definitively detect diversion of bomb quantities of plutonium or highly enriched uranium from open-quotes bulk handlingclose quotes facilities. There now exists a sizable body of unclassified technical reports, based on experimental results over many years, written by various experts, describing actual capabilities and limitations of safeguards techniques and systems, which collectively lead to definitive evaluations of technical safeguards effectiveness. For a large-scale operation of spent fuel reprocessing, plutonium fuel fabrication, or gas centrifuge uranium enrichment, an undisputable conclusion is that international safeguards systems would be unable to reliably and definitively detect the diversion in a one-year period of a significant quantity of plutonium or enriched uranium; moreover, diversion of many significant quantities per year (from such an operation) would have negligible probability of definitive detection if conducted in accordance with particle diversion scenarios. To properly inform the public and government agencies, reports on technical effectiveness of international safeguards should incorporate these basic conclusions

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

The international safeguards system and physical protection

International Nuclear Information System (INIS)

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

1990-02-01

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

Integrated international safeguards concepts for fuel reprocessing

International Nuclear Information System (INIS)

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

1981-12-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2015-04-07

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

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

International Nuclear Information System (INIS)

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

2015-01-01

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

International safeguards and nuclear terrorism

International Nuclear Information System (INIS)

Moglewer, S.

1987-01-01

This report provides a critical review of the effectiveness of International Atomic Energy Agency (IAEA) safeguards against potential acts of nuclear terrorism. The author argues that IAEA safeguards should be made applicable to deterring diversions of nuclear materials from civil to weapons purposes by subnational groups as well as by nations. Both technical and institutional factors are considered, and suggestions for organizational restructuring and further technical development are made. Awareness of the necessity for effective preventive measures is emphasized, and possible directions for further effort are suggested

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

Remote monitoring in international safeguards

International Nuclear Information System (INIS)

Dupree, S.A.; Sonnier, C.S.; Johnson, C.S.

1996-01-01

In recent years, technology that permits the integration of monitoring sensors and instruments into a coherent network has become available. Such integrated monitoring systems provide a means for the automatic collection and assessment of sensor signals and instrument readings and for processing such signals and readings in near real time. To gain experience with the new monitoring system technology, the US Department of energy, through bilateral agreements with its international partners, has initiated a project to emplace demonstration systems in various nuclear facilities and conduct field trials of the technology. This effort is the International Remote Monitoring Project. Under this project, remote monitoring systems are being deployed around the world in an incremental manner. Each deployment is different and each offers lessons for improving the performance and flexibility of the technology. Few problems were encountered with the operation of the installations to date, and much has been learned about the operation and use of the new technology. In the future, the authors believe systems for safeguards applications should be capable of being monitored remotely, emphasize the use of sensors, and utilize selective triggering for recording of images. Remote monitoring across national borders can occur only in the context of a cooperative, nonadversarial implementation regime. However, significant technical and policy work remains to be done before widespread safeguards implementation of remote monitoring should be considered. This paper shows that an abundance of technology supports the implementation of integrated and remote monitoring systems. Current field trials of remote monitoring systems are providing practical data and operational experience to aid in the design of tomorrow's systems

International safeguards for reprocessing plants. Final report

International Nuclear Information System (INIS)

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

1981-04-01

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

International safeguards for reprocessing plants. Final report

Energy Technology Data Exchange (ETDEWEB)

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

1981-04-01

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

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.

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

Authentication in the context of international safeguards

International Nuclear Information System (INIS)

Drayer, D.D.; Sonnier, C.S.; Augustson, R.

1991-01-01

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

The international framework for safeguarding peaceful nuclear energy programs

International Nuclear Information System (INIS)

Mazer, B.M.

1980-01-01

International law, in response to the need for safeguard assurances, has provided a framework which can be utilized by supplier and recipient states. Multilateral treaties have created the International Atomic Energy Agency which can serve a vital role in the establishment and supervision of safeguard agreements for nuclear energy programs. The Non-Proliferation Treaty has created definite obligations on nuclear-weapon and non-nuclear weapon states to alleviate some possibilities of proliferation and has rejuvenated the function of the IAEA in providing safeguards, especially to non-nuclear-weapon states which are parties to the Non-Proliferation treaty. States which are not parties to the Non-Proliferation Treaty may receive nuclear energy co-operation subject to IAEA safeguards. States like Canada, have insisted through the bilateral nuclear energy co-operation agreements that either individual or joint agreement be reached with the IAEA for the application of safeguards. Trilateral treaties among Canada, the recipient state and the IAEA have been employed and can provide the necessary assurances against the diversion of peaceful nuclear energy programs to military or non-peaceful uses. The advent of the Nuclear Suppliers Group and its guidlines has definitely advanced the cause of ensuring peaceful uses of nuclear energy. The ultimate objective should be the creation of an international structure incorporating the application of the most comprehensive safeguards which will be applied universally to all nuclear energy programs

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)

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

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

Containment/surveillance concepts for international safeguards in reprocessing plants

International Nuclear Information System (INIS)

Bleck, M.E.; Cameron, C.P.; Camp, A.L.

1980-01-01

This paper examines the potential role of advanced containment/surveillance instrumentation systems for international safeguards in reprocessing plants. Several conceptual systems for the surveillance of containment boundary penetrations in a reference reprocessing plant are described and evaluated. The results of the evaluation aid in understanding the potential capabilities and limitations of containment/surveillance as an international safeguards concept in this type of facility

Oak Ridge National Laboratory Office of International Nuclear Safeguards: Human Capital Development Activity in FY16

International Nuclear Information System (INIS)

Gilligan, Kimberly V.; Gaudet, Rachel N.

2016-01-01

In 2007, the U.S. Department of Energy National Nuclear Security Administration (DOE NNSA) Office of Nonproliferation and Arms Control (NPAC) completed a comprehensive review of the current and potential future challenges facing the international safeguards system. 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 (IAEA) General Conference, then Secretary of Energy Samuel W. Bodman announced the newly created Next Generation Safeguards Initiative (NGSI). NGSI consists of five program elements: policy development and outreach, concepts and approaches, technology and analytical methodologies, human capital development (HCD), and infrastructure development. This report addresses the HCD component of NGSI. The goal of the HCD component as defined in the NNSA Program Plan is ''to revitalize and expand the international safeguards human capital base by attracting and training a new generation of talent.'' The major objectives listed in the HCD goal include education and training, outreach to universities and professional societies, postdoctoral appointments, and summer internships at national laboratories.

Oak Ridge National Laboratory Office of International Nuclear Safeguards: Human Capital Development Activity in FY16

Energy Technology Data Exchange (ETDEWEB)

Gilligan, Kimberly V. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Nuclear Security and Isotope Technology Division; Gaudet, Rachel N. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Nuclear Security and Isotope Technology Division

2016-09-30

In 2007, the U.S. Department of Energy National Nuclear Security Administration (DOE NNSA) Office of Nonproliferation and Arms Control (NPAC) completed a comprehensive review of the current and potential future challenges facing the international safeguards system. 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 (IAEA) General Conference, then Secretary of Energy Samuel W. Bodman announced the newly created Next Generation Safeguards Initiative (NGSI). NGSI consists of five program elements: policy development and outreach, concepts and approaches, technology and analytical methodologies, human capital development (HCD), and infrastructure development. This report addresses the HCD component of NGSI. The goal of the HCD component as defined in the NNSA Program Plan is “to revitalize and expand the international safeguards human capital base by attracting and training a new generation of talent.” The major objectives listed in the HCD goal include education and training, outreach to universities and professional societies, postdoctoral appointments, and summer internships at national laboratories.

Development of an international safeguards approach to the final disposal of spent fuel in geological repositories

International Nuclear Information System (INIS)

Murphey, W.M.; Moran, B.W.; Fattah, A.

1996-01-01

The International Atomic Energy Agency (IAEA) is currently pursuing development of an international safeguards approach for the final disposal of spent fuel in geological repositories through consultants meetings and through the Program for Development of Safeguards for Final Disposal of Spent Fuel in Geological Repositories (SAGOR). The consultants meetings provide policy guidance to IAEA; SAGOR recommends effective approaches that can be efficiently implemented by IAEA. The SAGOR program, which is a collaboration of eight Member State Support Programs (MSSPs), was initiated in July 1994 and has identified 15 activities in each of three areas (i.e. conditioning facilities, active repositories, and closed repositories) that must be performed to ensure an efficient, yet effective safeguards approach. Two consultants meetings have been held: the first in May 1991 and the last in November 1995. For nuclear materials emplaced in a geological repository, the safeguards objectives were defined to be (1) to detect the diversion of spent fuel, whether concealed or unconcealed, from the repository and (2) to detect undeclared activities of safeguards concern (e.g., tunneling, underground reprocessing, or substitution in containers)

Croatian Support for Strengthening International Safeguards

International Nuclear Information System (INIS)

Cizmek, Ankica; Novosel, Nevenka

2010-01-01

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

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

International safeguards and international nuclear trade

International Nuclear Information System (INIS)

Felten, P.

1991-01-01

A particular feature of nuclear trade is the need to ensure a good equilibrium between technology transfer and the requirements linked to non proliferation of nuclear weapons. The recent dramatic changes that occurred on the international scene have particularly underlined the difficulty to reach this equilibrium, reminding us the fragility of the existing order and the responsibility of the nuclear community in the field of non-proliferation. Consequently, there is a need for an international thorough review of the actual non proliferation tools developed until now. This review could lead to reconsider some of the dogmas upon which the present safeguard system is based

International safeguards for spent fuel storage

International Nuclear Information System (INIS)

Kratzer, M.; Wonder, E.; Immerman, W.; Crane, F.

1981-08-01

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

Canada and international safeguards. Verifying nuclear non-proliferation. Verification brochure no. 5

Energy Technology Data Exchange (ETDEWEB)

1990-01-01

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

Preliminary concepts: materials management in an internationally safeguarded nuclear-waste geologic repository

International Nuclear Information System (INIS)

Ostenak, C.A.; Whitty, W.J.; Dietz, R.J.

1979-11-01

Preliminary concepts of materials accountability are presented for an internationally safeguarded nuclear-waste geologic repository. A hypothetical reference repository that receives nuclear waste for emplacement in a geologic medium serves to illustrate specific safeguards concepts. Nuclear wastes received at the reference repository derive from prior fuel-cycle operations. Alternative safeguards techniques ranging from item accounting to nondestructive assay and waste characteristics that affect the necessary level of safeguards are examined. Downgrading of safeguards prior to shipment to the repository is recommended whenever possible. The point in the waste cycle where international safeguards may be terminate depends on the fissile content, feasibility of separation, and practicable recoverability of the waste: termination may not be possible if spent fuels are declared as waste

Safeguards First Principle Initiative (SFPI) Cost Model

International Nuclear Information System (INIS)

Price, Mary Alice

2010-01-01

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

Implementation of a Strengthened International Safeguards System. ABACC 15 Years

International Nuclear Information System (INIS)

Vicens, H.R.; Maceiras, E.; Dominguez, C.A.

2011-01-01

The purpose of the paper is to explain how the system of a regional safeguard has been operating and developing in the framework of the Brazilian-Argentine Agency of Accounting and control of nuclear Materials (ABACC), and how the international recommendations of radiological protection must be taken into account in the safeguards implementation and its impact in the international context.

Understanding national and international safeguards: an evolutionary process

International Nuclear Information System (INIS)

Higinbotham, W.A.

1983-01-01

Domestic and international safeguards have been evolving and will continue to evolve. in the case of the United States, the concern was to protect the classified materials, at first. Then attention focussed on material accounting, then on measures to promptly detect theft by individuals with access, and later on physical protection to ward-off armed terrorists. The objective of the IAEA has always been to provide assurance that nuclear materials are not being diverted from the peaceful facilities that are under safeguards. The evolution has taken place in deciding how to provide this assurance, and in the definition of specific safeguards goals. In both cases the technology needed to meet the goals has improved due to R and D and to experience. A plea is made for more cooperation betwen those who develop and manage the policies, those who develop safeguards techniques, and those who are subject to national and IAEA safeguards. Some illustrations of the evolution of policies, inadequate coordination and general progress are given

Implementation of a Strengthened International Safeguards System ABBAC 15 years

International Nuclear Information System (INIS)

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

2008-01-01

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

Update on Monitoring Technologies for International Safeguards and Fissile Material Verification

International Nuclear Information System (INIS)

Croessmann, C. Dennis; Glidewell, Don D.; Mangan, Dennis L.; Smathers, Douglas C.

1999-01-01

Monitoring technologies are playing an increasingly important part in international safeguards and fissile material verification. The developments reduce the time an inspector must spend at a site while assuring continuity of knowledge. Monitoring technologies' continued development has produced new seal systems and integrated video surveillance advances under consideration for Trilateral Initiative use. This paper will present recent developments for monitoring systems at Embalse, Argentina, VNHEF, Sarov, Russian, and Savannah River Site, Aiken, South Carolina

UF/sub 6/ test loop for evaluation and implementation of international enrichment plant safeguards

International Nuclear Information System (INIS)

Cooley, J.N.; Fields, L.W.; Swindle, D.W. Jr.

1987-01-01

A functional test loop capable of simulating UF/sub 6/ flows, pressures, and pipe deposits characteristic of gas centrifuge enrichment plant piping has been designed and fabricated by the Enrichment Safeguards Program of Martin Marietta Energy Systems, Inc., for use by the International Atomic Energy Agency (IAEA) at its Safeguards Analytical Laboratory in Seibersdorf, Austria. The purpose of the test loop is twofold: (1) to enable the IAEA to evaluate and to calibrate enrichment safeguards measurement instrumentation to be used in limited frequency-unannounced access (LFUA) inspection strategy measurements at gas centrifuge enrichment plants and (2) to train IAEA inspectors in the use of such instrumentation. The test loop incorporates actual sections of cascade header pipes from the centrifuge enrichment plants subject to IAEA inspections. The test loop is described, applications for its use by the IAEA are detailed, and results from an initial demonstration session using the test loop are summarized. By giving the IAEA the in-house capability to evaluate LFUA inspection strategy approaches, to develop inspection procedures, to calibrate instrumentation, and to train inspectors, the UF/sub 6/ cascade header pipe test loop will contribute to the IAEA's success in implementing LFUA strategy inspections at gas centrifuge enrichment facilities subject to international safeguards inspections

International safeguards: Accounting for nuclear materials

Energy Technology Data Exchange (ETDEWEB)

Fishbone, L.G.

1988-09-28

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

International safeguards: Accounting for nuclear materials

International Nuclear Information System (INIS)

Fishbone, L.G.

1988-01-01

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

UF6 test loop for evaluation and implementation of international enrichment plant safeguards

International Nuclear Information System (INIS)

Cooley, J.N.; Fields, L.W.; Swindle, D.W. Jr.

1987-06-01

A functional test loop capable of simulating UF 6 flows, pressures, and pipe deposits characteristic of gas centrifuge enrichment plant piping has been designed and fabricated by the Enrichment Safeguards Program of Martin Marietta Energy Systems, Inc., for use by International Atomic Energy Agency (IAEA) at its Safeguards Analytical Laboratory in Seibersdorf, Austria. Purpose of the test loop is twofold: (1) to enable the IAEA to evaluate and to calibrate enrichment safeguards measurement instrumentation to be used in limited frequency-unannounced access (LFUA) inspection strategy measurements at gas centrifuge enrichment plants and (2) to train IAEA inspectors in the use of such instrumentation. The test loop incorporates actual sections of cascade header pipes from the centrifuge enrichment plants subject to IAEA inspections. The test loop is described, applications for its use by the IAEA are detailed, and results from an initial demonstration session using the test loop are summarized

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

International Nuclear Information System (INIS)

Stanford, Dennis

2007-01-01

This paper documents issues Nuclear Fuel Services, Inc. has addressed in the performance of international work to safeguards and security work. It begins with a description of the package we put together for a sample proposal for the Global Threat Reduction Initiative, for which we were ranked number one for technical approach and cost, and concludes with a discussion of approaches that we have taken to performing this work, including issues related to performing the work as part of a team. The primary focus is on communication, workforce, equipment, and coordination issues. Finally, the paper documents the rules that we use to assure the work is performed safely and successfully. (author)

Lessons Learned in International Safeguards - Implementation of Safeguards at the Rokkasho Reprocessing Plant

International Nuclear Information System (INIS)

Ehinger, Michael H.; Johnson, Shirley

2010-01-01

The focus of this report is lessons learned at the Rokkasho Reprocessing Plant (RRP). However, the subject of lessons learned for application of international safeguards at reprocessing plants includes a cumulative history of inspections starting at the West Valley (New York, U.S.A.) reprocessing plant in 1969 and proceeding through all of the efforts over the years. The RRP is the latest and most challenging application the International Atomic Energy Agency has faced. In many ways the challenges have remained the same, timely inspection and evaluation with limited inspector resources, with the continuing realization that planning and preparations can never start early enough in the life cycle of a facility. Lessons learned over the years have involved the challenges of using ongoing advances in technology and dealing with facilities with increased throughput and continuous operation. This report will begin with a review of historical developments and lessons learned. This will provide a basis for a discussion of the experiences and lessons learned from the implementation of international safeguards at RRP.

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

Swedish experiences in implementing national and international safeguards

International Nuclear Information System (INIS)

Nilsson, A.; Elborn, M.; Grahn, P.

1991-01-01

This paper reports that international safeguards have been applied in Sweden since the early 70s. Experiences have been achieved from exclusive bilateral and trilateral control followed by NPT safeguards in 1975. The Swedish State System for accountancy and Control (SSAC) includes all regulations that follows from prevailing obligations regarding the peaceful uses of nuclear material. The system has been developed in cooperation between the national authority, the Swedish Nuclear Power Inspectorate (SKI) and the Swedish nuclear industry. The paper presents experiences from the practical implementation of the SSAC and the IAEA safeguards system, gained by the SKI and the nuclear industry, respectively. Joint approaches and solutions to some significant safeguards issues are presented. The cooperation between the nuclear industry and the authority in R and D activities, in particular with respect to the Swedish Support Program is highlighted, e.g. the use of nuclear facilities in development or training tasks. some of the difficulties encountered with the system are also touched upon

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

International Nuclear Information System (INIS)

Larrimore, J.A.

1995-01-01

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

International training course on nuclear materials accountability for safeguards purposes

International Nuclear Information System (INIS)

1980-12-01

The two volumes of this report incorporate all lectures and presentations at the International Training Course on Nuclear Materials Accountability and Control for Safeguards Purposes, held May 27-June 6, 1980, at the Bishop's Lodge near Santa Fe, New Mexico. The course, authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, was developed to provide practical training in the design, implementation, and operation of a National system of nuclear materials accountability and control that satisfies both National and IAEA International safeguards objectives. Volume I, covering the first week of the course, presents the background, requirements, and general features of material accounting and control in modern safeguard systems. Volume II, covering the second week of the course, provides more detailed information on measurement methods and instruments, practical experience at power reactor and research reactor facilities, and examples of operating state systems of accountability and control

International training course on nuclear materials accountability for safeguards purposes

Energy Technology Data Exchange (ETDEWEB)

1980-12-01

The two volumes of this report incorporate all lectures and presentations at the International Training Course on Nuclear Materials Accountability and Control for Safeguards Purposes, held May 27-June 6, 1980, at the Bishop's Lodge near Santa Fe, New Mexico. The course, authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, was developed to provide practical training in the design, implementation, and operation of a National system of nuclear materials accountability and control that satisfies both National and IAEA International safeguards objectives. Volume I, covering the first week of the course, presents the background, requirements, and general features of material accounting and control in modern safeguard systems. Volume II, covering the second week of the course, provides more detailed information on measurement methods and instruments, practical experience at power reactor and research reactor facilities, and examples of operating state systems of accountability and control.

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.

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

Interim Procedures Safeguarding Mobile Devices during International Travel

Science.gov (United States)

This procedure is for safeguarding EPA information and systems for all employees, contractors, and other users while on international travel or to specifically designated locations within the United States and foreign embassies.

International Atomic Energy Agency use of facility calorimeters for safeguards purposes

International Nuclear Information System (INIS)

McRae, L.P.; Delegard, C.H.; Hamilton, R.A.; Westsik, G.A.; Moriarty, T.F.; Lemaire, R.J.

1996-01-01

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

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

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.

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)

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)

Problem statement: international safeguards for a light-water reactor fuels reprocessing plant

International Nuclear Information System (INIS)

Shipley, J.P.; Hakkila, E.A.; Dietz, R.J.; Cameron, C.P.; Bleck, M.E.; Darby, J.L.

1979-03-01

This report considers the problem of developing international safeguards for a light-water reactor (LWR) fuel reprocessing/conversion facility that combines the Purex process with conversion of plutonium nitrate to the oxide by means of plutonium (III) oxalate precipitation and calcination. Current international safeguards systems are based on the complementary concepts of materials accounting and containment and surveillance, which are designed to detect covert, national diversion of nuclear material. This report discusses the possible diversion threats and some types of countermeasures, and it represents the first stage in providing integrated international safeguards system concepts that make optimum use of available resources. The development of design methodology to address this problem will constitute a significant portion of the subsequent effort. Additionally, future technology development requirements are identified. 8 figures, 1 table

International nuclear material safeguards

International Nuclear Information System (INIS)

Syed Azmi Syed Ali

1985-01-01

History can be a very dull subject if it relates to events which have long since lost their relevance. The factors which led to the creation of the International Atomic Energy Agency (IAEA), however, are as important and relevant today as they were when the Agency was first created. Without understanding these factors it is impossible to realise how important the Agency is in the present world or to understand some of the controversies surrounding its future. Central to these controversies is the question of how best to promote the international transfer of nuclear technology without contributing further to the problem of proliferating nuclear explosives or explosive capabilities. One effective means is to subject nuclear materials (see accompanying article in box), which forms the basic link between the manufacture of nuclear explosives and nuclear power generation, to international safeguards. This was realized very early in the development of nuclear power and was given greater emphasis following the deployment of the first two atomic bombs towards the end of World War II. (author)

International Atomic Energy agency use of facility calorimeters for safeguards purposes

International Nuclear Information System (INIS)

Mcrae, L.P.

1996-01-01

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

Feasibility Study of Implementing a Mobile Collaborative Information Platform for International Safeguards Inspections

Energy Technology Data Exchange (ETDEWEB)

Gastelum, Zoe N. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Gitau, Ernest T. N. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Doehle, Joel R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Toomey, Christopher M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2014-09-01

In response to the growing pervasiveness of mobile technologies such as tablets and smartphones, the International Atomic Energy Agency and the U.S. Department of Energy National Laboratories have been exploring the potential use of these platforms for international safeguards activities. Specifically of interest are information systems (software, and accompanying servers and architecture) deployed on mobile devices to increase the situational awareness and productivity of an IAEA safeguards inspector in the field, while simultaneously reducing paperwork and pack weight of safeguards equipment. Exploratory development in this area has been met with skepticism regarding the ability to overcome technology deployment challenges for IAEA safeguards equipment. This report documents research conducted to identify potential challenges for the deployment of a mobile collaborative information system to the IAEA, and proposes strategies to mitigate those challenges.

International Atomic Energy Agency Safeguards: Challenge and response

Science.gov (United States)

Spector, Leonard S.

2017-11-01

This article provides a critical review of the nuclear accounting and inspection system of the International Atomic Energy Agency (IAEA), known as "IAEA safeguards." The article focuses on the multiple challenges the Agency confronts in verifying that all nuclear activities in the countries under its safeguards system are being pursued for exclusively peaceful purposes. The principal challenges noted are those posed by: undeclared facilities, the development of enrichment and reprocessing capabilities, illicit procurement activities, denial of inspector access, difficulties in verifying absence of weaponization activities, and difficulties in establishing that all nuclear-relevant activities in a state are peaceful. The article is in the form of annotated PowerPoint briefing slides.

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

Energy Agency safeguards into the design of nuclear facilities. This paper describes the work that has been completed in the development of a Safeguards by Design process for a project, illustrated by flow diagrams based upon the project phases described in U.S. Department of Energy Order 413.3A, Program and Project Management for the Acquisition of Capital Assets. The institutionalization of the Safeguards by Design process directly supports the goals of the Next Generation Safeguards Initiative and also aligns with goals and objectives of the International Atomic Energy Agency. Other benefits from institutionalizing this Safeguards by Design process are discussed within this paper

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

International Nuclear Information System (INIS)

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

2010-01-01

The International Nuclear Safeguards and Engagement Program (INSEP), the international outreach component of the Next Generation Safeguards Initiative (NGSI), is a collaborative program that endeavors to strengthen international safeguards at all stages of nuclear development. One of the critical ways the program achieves this objective is through working with partners to increase the effectiveness of the State System of Accountancy for and Control of Nuclear Materials (SSAC) - the essential elements of national, regulatory and facility safeguards competencies that work as a system to provide the International Atomic Energy Agency (IAEA) and the world the full assurance of the state's adherence to its safeguards agreements. INSEP provides assistance in developing a state's SSAC in a number of areas, from developing national legislation governing the possession and use of nuclear material to working with nuclear facility operators to developing good practices in waste management. INSEP has collaborated with foreign partners in peaceful nuclear applications for over two decades, but recently, it has focused its efforts on strengthening SSACs due to the growth of nuclear power worldwide, particularly in countries with limited nuclear infrastructures. This new area of focus has prompted INSEP to develop a model of SSAC competencies that will serve not only as a structure for its engagement with partner states, but also as a means to facilitate coordination with other states that provide training and assistance, and as a mechanism for evaluating the effectiveness of its work in reaching its intended objectives. While this model uses as its starting point the requirements on a State that are presented in the Comprehensive Safeguards Agreement and the Additional Protocol, it is not, in itself, a requirements document or guidance for implementing requirements. It is rather an analysis of what capabilities will be needed in a State to be able to meet requirements and to

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.

13 CFR 108.506 - Safeguarding the NMVC Company's assets/Internal controls.

Science.gov (United States)

2010-01-01

... assets/Internal controls. 108.506 Section 108.506 Business Credit and Assistance SMALL BUSINESS... Requirements § 108.506 Safeguarding the NMVC Company's assets/Internal controls. You must adopt a plan to... document describing your control procedures. ...

Developing the Next Generation of International Safeguards and Nonproliferation Experts: Highlights of Select Activities at the National Laboratories

Energy Technology Data Exchange (ETDEWEB)

Reed, J; Mathews, C; Kirk, B; Lynch, P; Doyle, J; Meek, E; Pepper, S; Metcalf, R

2010-03-31

With many safeguards experts in the United States at or near retirement age, and with the growing and evolving mission of international safeguards, attracting and educating a new generation of safeguards experts is an important element of maintaining a credible and capable international safeguards system. The United States National Laboratories, with their rich experience in addressing the technical and policy challenges of international safeguards, are an important resource for attracting, educating, and training future safeguards experts. This presentation highlights some of the safeguards education and professional development activities underway at the National Laboratories. These include university outreach, summer courses, internships, mid-career transition, knowledge retention, and other projects. The presentation concludes with thoughts on the challenge of interdisciplinary education and the recruitment of individuals with the right balance of skills and backgrounds are recruited to meet tomorrow's needs.

Lessons Learned from the Development of an Example Precision Information Environment for International Safeguards

Energy Technology Data Exchange (ETDEWEB)

Gastelum, Zoe N. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Henry, Michael J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Burtner, IV, E. R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Doehle, J. R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Hampton, S. D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); La Mothe, R. R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Nordquist, P. L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Zarzhitsky, D. V. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2014-12-01

The International Atomic Energy Agency (IAEA) is interested in increasing capabilities of IAEA safeguards inspectors to access information that would improve their situational awareness on the job. A mobile information platform could potentially provide access to information, analytics, and technical and logistical support to inspectors in the field, as well as providing regular updates to analysts at IAEA Headquarters in Vienna or at satellite offices. To demonstrate the potential capability of such a system, Pacific Northwest National Laboratory (PNNL) implemented a number of example capabilities within a PNNL-developed precision information environment (PIE), and using a tablet as a mobile information platform. PNNL’s safeguards proof-of-concept PIE intends to; demonstrate novel applications of mobile information platforms to international safeguards use cases; demonstrate proof-of-principle capability implementation; and provide “vision” for capabilities that could be implemented. This report documents the lessons learned from this two-year development activity for the Precision Information Environment for International Safeguards (PIE-IS), describing the developed capabilities, technical challenges, and considerations for future development, so that developers working to develop a similar system for the IAEA or other safeguards agencies might benefit from our work.

Lessons Learned from the Development of an Example Precision Information Environment for International Safeguards

International Nuclear Information System (INIS)

Gastelum, Zoe N.; Henry, Michael J.; Burtner, IV E.R.; Doehle, J. R.; Hampton, S. D.; La Mothe, R. R.; Nordquist, P. L.; Zarzhitsky, D. V.

2014-01-01

The International Atomic Energy Agency (IAEA) is interested in increasing capabilities of IAEA safeguards inspectors to access information that would improve their situational awareness on the job. A mobile information platform could potentially provide access to information, analytics, and technical and logistical support to inspectors in the field, as well as providing regular updates to analysts at IAEA Headquarters in Vienna or at satellite offices. To demonstrate the potential capability of such a system, Pacific Northwest National Laboratory (PNNL) implemented a number of example capabilities within a PNNL-developed precision information environment (PIE), and using a tablet as a mobile information platform. PNNL's safeguards proof-of-concept PIE intends to; demonstrate novel applications of mobile information platforms to international safeguards use cases; demonstrate proof-of-principle capability implementation; and provide ''vision''@ for capabilities that could be implemented. This report documents the lessons learned from this two-year development activity for the Precision Information Environment for International Safeguards (PIE-IS), describing the developed capabilities, technical challenges, and considerations for future development, so that developers working to develop a similar system for the IAEA or other safeguards agencies might benefit from our work.

Proposal of a national system to supervise nuclear installations out of international safeguards

International Nuclear Information System (INIS)

Rosa, L.P.

1990-01-01

It is proposed a national system to safeguard, supervise and inspect nuclear facilities in Brazil, apart from international safeguards. It discusses also the military nuclear activities and the uranium enrichment plants. The system should be controlled by Brazilian CNEN. (A.C.A.S.)

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.

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

Negotiating supranational rules - The genesis of the International Atomic Energy Agency Safeguards System

Energy Technology Data Exchange (ETDEWEB)

Forland, Astrid

1998-12-31

The object of this thesis 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 evolution is traced not through the practical implementation of the safeguards system, but through the various multilateral negotiations through which it was created. The focus is on analysing the arguments advanced in the various negotiations, and the main objective is to single out the factors determining the result. The discussion is organised into the following chapters: (1) The statute of the IAEA, (2) The IAEA 1961 safeguard document (INFCIRC/26), (3) The IAEA 1965 safeguards document (INFCIRC/66), (4) The non-proliferation treaty, (5) NPT safeguards. 92 refs.

Negotiating supranational rules - The genesis of the International Atomic Energy Agency Safeguards System

Energy Technology Data Exchange (ETDEWEB)

Forland, Astrid

1999-12-31

The object of this thesis 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 evolution is traced not through the practical implementation of the safeguards system, but through the various multilateral negotiations through which it was created. The focus is on analysing the arguments advanced in the various negotiations, and the main objective is to single out the factors determining the result. The discussion is organised into the following chapters: (1) The statute of the IAEA, (2) The IAEA 1961 safeguard document (INFCIRC/26), (3) The IAEA 1965 safeguards document (INFCIRC/66), (4) The non-proliferation treaty, (5) NPT safeguards. 92 refs.

National and international safety, safeguardability and security

International Nuclear Information System (INIS)

Wakabayashi, Hiroaki

1987-01-01

All nuclear power and fuel cycle facility development must comply with the predecided national regulation and security codes which each country's Atomic Energy Commission stipulates. Those codes will basically evolve as technologies and the social system will develop, change and shift. It is also to be noted that the IAEA's international guidelines have been adopted particularly by developing countries as a good reference for their proper establishment of their safety codes. The report first discusses the plant safety regulation of the inherently safe reactors in comparison to the existing code (or licensing guide) of the Japanese government. Then the new trend seen now in a regulatory body (the US NRC) is reviewed and a proposal of the smooth transition into the new philosophy is presented. In the second part of the paper, the fuel safeguarding and facility security (or physical protection) are discussed, because in the case of inherently safe reactors like ISER-PIUS, it seems that safety has much more to do with the safeguard and the security. In the third part, the international relevances to the security of the ISER-PIUS are discussed, because any ISER-PIUS will be meaningless unless they are used extensively and freely in any part of the world precluding the security concerns. In collaborative use of the state and international codes, regulatory guides and practices, it is evident that ISER-PIUS system can clear the requirements on all the aspects by ample margin. (Nogami, K.)

University of Texas Safeguards by Design Problem Statement

Energy Technology Data Exchange (ETDEWEB)

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

2018-01-22

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

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)

Safeguarding nuclear energy in the Pacific: the role of Australia

International Nuclear Information System (INIS)

Indyk, M.

1980-01-01

Measures necessary for the establishment of an effective safeguards regime are outlined. These include the establishment of multinational institutions to control and limit the number of sensitive facilities, the establishment of regional spent fuel storage sites and regional plutonium banks to be placed under international control, the establishment of international uranium banks to provide fuel assurances to cooperating countries and the cooperation between suppliers and consumers in improving safeguard techniques. The possibility of a Pacific regional non-proliferation initiative and the role Australia is likely to play in such an initiative are considered. From the public record, the Australian Government would appear to be a deeply committed supporter of international measures to control reprocessing, to store spent fuel and plutonium, to strengthen safeguards and to provide fuel assurances to consumers. However, the Government's actions are not as consistent. It is concluded that Australia will be willing to support non-proliferation efforts as long as they do not unduly jeopardise uranium exports

An American Academy for Training Safeguards Inspectors - An Idea Revisited

International Nuclear Information System (INIS)

Durst, Philip Casey; Bean, Robert

2010-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2017-06-01

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

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

International Nuclear Information System (INIS)

Long, J.D.

2013-01-01

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

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

Selected nondestructive assay instrumentation for an international safeguards system at uranium enrichment plants

International Nuclear Information System (INIS)

Tape, J.W.; Baker, M.P.; Strittmatter, R.; Jain, M.; Evans, M.L.

1979-01-01

A selected set of nondestructive assay instruments for an international safeguards system at uranium enrichment plants is currently under development. These instruments are of three types: in-line enrichment meters for feed, product, and tails streams; area radiation monitors for direct detection of high-enriched uranium production, and an enrichment meter for spent alumina trap material. The current status of the development of each of these instruments is discussed, with supporting data, as well as the role each would play in a total international safeguards system. 5 figures

USSP-IAEA WORKSHOP ON ADVANCED SENSORS FOR SAFEGUARDS

International Nuclear Information System (INIS)

PEPPER, S.; QUEIROLO, A.; ZENDEL, M.; WHICHELLO, J.; ANNESE, C.; GRIEBE, J.; GRIEBE, R.

2007-01-01

The IAEA Medium Term Strategy (2006-2011) defines a number of specific goals in respect to the IAEA's ability to provide assurances to the international community regarding the peaceful use of nuclear energy through States adherences to their respective non-proliferation treaty commitments. The IAEA has long used and still needs the best possible sensors to detect and measure nuclear material. The Department of Safeguards, recognizing the importance of safeguards-oriented R and D, especially targeting improved detection capabilities for undeclared facilities, materials and activities, initiated a number of activities in early 2005. The initiatives included letters to Member State Support Programs (MSSPs), personal contacts with known technology holders, topical meetings, consultant reviews of safeguards technology, and special workshops to identify new and novel technologies and methodologies. In support of this objective, the United States Support Program to IAEA Safeguards hosted a workshop on ''Advanced Sensors for Safeguards'' in Santa Fe, New Mexico, from April 23-27, 2007. The Organizational Analysis Corporation, a U.S.-based management consulting firm, organized and facilitated the workshop. The workshop's goal was to help the IAEA identify and plan for new sensors for safeguards implementation. The workshop, which was attended by representatives of seven member states and international organizations, included presentations by technology holders and developers on new technologies thought to have relevance to international safeguards, but not yet in use by the IAEA. The presentations were followed by facilitated breakout sessions where the participants considered two scenarios typical of what IAEA inspectors might face in the field. One scenario focused on an enrichment plant; the other scenario focused on a research reactor. The participants brainstormed using the technologies presented by the participants and other technologies known to them to propose

National viewpoints: Views on strengthened safeguards from Australia, Cuba and South Africa

International Nuclear Information System (INIS)

Biggs, I.; Saburido, E.F.; Mxakato-Diseko, N.J.

1999-01-01

This paper presents views of Australia, Cuba and South Africa concerned with strengthened safeguards regime. Australia has been involved with the IAEA safeguards system since the first plenary meeting of the Conference on the IAEA Statute in 1956, joined the NPT in 1973 and began concluding bilateral safeguards agreements in 1977. Australia has the greatest respect for the IAEA coordinated efforts started in 1998 to strengthen and integrate the safeguards system. Cuba has always attached special importance to nuclear safeguards activities, recognizing their high priority as well as the important role they have in respect to international disarmament and security. South Africa supports the efforts in strengthening the safeguards activities and remains hopeful that the international community will address the challenges posed by the Trilateral Initiative between Russian federation, USA and IAEA in a mature and cooperative way

Use of fuel reprocessing plant instrumentation for international safeguards

International Nuclear Information System (INIS)

Ayers, A.L.

1977-01-01

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

Safeguards-By-Design: Guidance and Tools for Stakeholders

Energy Technology Data Exchange (ETDEWEB)

Mark Schanfein; Shirley Johnson

2012-02-01

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

Safeguards-By-Design: Guidance and Tools for Stakeholders

International Nuclear Information System (INIS)

Schanfein, Mark; Johnson, Shirley

2012-01-01

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

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

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

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)

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

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.

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

Energy Technology Data Exchange (ETDEWEB)

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

2009-09-01

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

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

International Nuclear Information System (INIS)

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

1987-03-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1987-03-01

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

Nuclear development and international safeguards: where do we stand and where are we going

International Nuclear Information System (INIS)

Scheinman, L.

1979-01-01

Together with the political commitments reflected in the Nonproliferation Treaty, international safeguards represent a cornerstone of an effective international nuclear regime. As important as they are, safeguards cannot fully achieve the goal of maintaining access to peaceful nuclear energy without significantly increasing proliferation risks. In order to mitigate those risks, extrinsic protective measures are necessary, including the establishment of rules, norms and institutional arrangements relating to the timing, conditions, and scope of introduction of sensitive nuclear fuels and fuel cycle facilities

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

Safeguards by design - The early consideration of safeguards concepts

International Nuclear Information System (INIS)

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

2009-01-01

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

The Department of Safeguards Quality Management System

International Nuclear Information System (INIS)

Konecni, S.

2015-01-01

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

International safeguards: experience and prospects

International Nuclear Information System (INIS)

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

1982-01-01

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

US enrichment safeguards program development activities with potential International Atomic Energy Agency safeguards applications. Part 1. Executive summaries

International Nuclear Information System (INIS)

Swindle, D.W. Jr.

1984-07-01

The most recent progress, results, and plans for future work on the US Enrichment Safeguards Program's principal development activities are summarized. Nineteen development activities are reported that have potential International Atomic Energy Agency (IAEA) safeguards applications. Part 1 presents Executive Summaries for these, each of which includes information on (1) the purpose and scope of the development activity; (2) the potential IAEA safeguards application and/or use if adopted; (3) significant development work, results, and/or conclusions to date; and where appropriate (4) future activities and plans for continued work. Development activities cover: measurement technology for limited-frequency-unannounced-access stategy inspections; integrated data acquisition system; enrichment-monitoring system; load-cell-based weighing system for UF 6 cylinder mass verifications; vapor phase versus liquid phase sampling of UF 6 cylinders; tamper-safing hardware and systems; an alternative approach to IAEA nuclear material balance verifications resulting from intermittent inspections; UF 6 sample bottle enrichment analyzer; crated waste assay monitor; and compact 252 Cf shuffler for UF 6 measurements

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

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

International Nuclear Information System (INIS)

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

2009-01-01

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

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 non-proliferation

International Nuclear Information System (INIS)

Harry, R.J.S.

1995-02-01

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

IAEA safeguards and non-proliferation

Energy Technology Data Exchange (ETDEWEB)

Harry, R J.S.

1995-02-01

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

Lessons from post-war Iraq for the international full-scope safeguards regime

International Nuclear Information System (INIS)

Scheinman, L.

1993-01-01

The discovery after the Gulf War of the extensive Iraqi nuclear weapon program severely shook public confidence in the nuclear non-proliferation regime in general, and the safeguards program of the IAEA under the nuclear Non-Proliferation Treaty, in particular. Iraq provided the justification for evaluating the safeguards regime under new political circumstances, so that appropriate corrective measures could be taken when necessary. It is now up to the individual states within the international system to take advantage of this opportunity

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

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

International safeguards in large-scale nuclear facilities

International Nuclear Information System (INIS)

Gupta, D.; Heil, J.

1977-01-01

The trend in the energy sector in most of the world's industrialized areas shows rather clearly that the rate of installing nuclear plants will be very high and that the largest possible units of nuclear material handling and storage facilities will be built. Various experiments and analyses of measurement methods relevant to safeguards in typical nuclear facilities such as a fuel reprocessing or a fabrication plant have shown that the associated measurement errors as obtained under normal operating conditions are such that they are mainly dominated by systematic errors, which may lie in the range of percentages of the measured amount so that a material balance in such a plant could not normally be closed with any higher accuracy. For example, in a reprocessing plant with a throughput of 1500t U/a and a corresponding throughput of 15t Pu/a, a systematic error of 1% would cause a measurement uncertainty of around 70kg Pu in case a material balance is struck twice a year. Such a large amount may be considered to be unacceptable from the point of view of international safeguards since it arises out of a single plant. The simplest way of getting around the problem would be to strike a material balance more frequently over a given period. This could, however, lead to an enormous increase in the technical and financial burden for the operator of a facility. This paper analyses this problem in some detail for some facilities and shows that, for example, with a properly developed information system in such plants and a combination of containment, surveillance and accountancy measures, a safeguards system can be built up for such facilities. (author)

International safeguards in nuclear weapon states - Status and look into the future

International Nuclear Information System (INIS)

Jorant, C.

2013-01-01

This paper shall recall the framework for the application of international safeguards in the 5 Nuclear Weapons States (USA, Russia, China, United-Kingdom and France) and give an overview on their implementation. It shall then discuss some reasons for an evolution of those States and IAEA's commitments to apply its safeguards and suggests ideas for an increased but efficient involvement of IAEA in those States fully taking into account the specificities of those States within the State Level Approach.The paper is followed by the slides of the presentation. (author)

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

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)

Work Group 1: Future Directions for International Safeguards

International Nuclear Information System (INIS)

Casterton, J.; Meylemans, P.

2013-01-01

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

The potential value of dynamic materials control in international safeguards

International Nuclear Information System (INIS)

Keepin, G.R.; Lovett, J.E.

1979-01-01

The difficulties inherent in conventional materials accountancy based on semi-annual or annual shutdown cleanout physical inventories have been recognized for many years. The increasing importance of international nuclear materials safeguards, coupled with the availability of advanced non-destructive measurement technology which could be installed on or near process lines, has led to the development of the concept of advanced or dynamic materials control. The potential benefits of dynamic materials control in terms of significantly improved detection capabilities (ranging from a few kilograms of plutonium down to perhaps a few hundred grams, even for large-scale bulk processing facilities), and even more dramatically improved detection timeliness (typically a few days, and potentially only a few hours, in advanced facilities), are reviewed. At least twelve major dynamic material control systems already in existence or in the process of being installed are noted, and some of the essential characteristics are discussed. Some currently unresolved questions are explored, and future prospects for the concept of dynamic material control in international safeguards are reviewed. (author)

An ESARDA view of future implementation of science and modern technology for safeguards following recent ESARDA and INMM initiatives

International Nuclear Information System (INIS)

Guardini, Sergio; Stein, Gotthard

2001-01-01

Full text: The new challenges posed by integrated safeguards, ensuring correctness and completeness without cost increase, may require that new techniques are employed or existing techniques modified to cope with the new requirements. Conscious of this new scenario, ESARDA decided to undertake a thorough review of current Science and Technology initiatives aimed, in particular, at identifying new techniques not yet applied in Safeguards that could help in increasing efficiency and effectiveness at no additional cost. To that purpose ESARDA organized, together with the INMM, a series of workshops on 'Science and Modem Technology for Safeguards' with the aim 'to inform the safeguards community about selected sciences and advanced technologies that are currently available or that will become available in the next few years and that could be used to support needed advances in international safeguards' and to 'stimulate interchange amongst experts in the various technologies and in safeguards'. Three Workshops have been held, the first in Arona in October 1996, then at Albuquerque, September 1998 and the third in Tokyo, November 2000. In 1998 ESARDA also dedicated an annual meeting, in Helsinki, to the topic, 'Modem Verification Regimes: Similarities, Synergies and Challenges'. The ESARDA Co-ordinators have examined the outcome of these Workshops to establish whether the aims were achieved, analyzing the status of the development of those techniques and methods presented that may have an application for Safeguards and suggesting future directions for the ESARDA activities and for Safeguards R and D. Following the main format followed by the Workshops, the Co-ordinators' analysis has been structured along the following areas: 1. 'hard' sciences (instruments, C and S); 2. 'soft' sciences (data and information treatment, knowledge building); 3. nontechnical (or socio-political) aspects; 4. the role of the Regional Systems of Accountancy and Control (RSAC) and of the State

The ‘Landscape’ of Nuclear Safeguards: A Comparative Analysis of the International and Regional Systems

International Nuclear Information System (INIS)

Colussi, I.A.

2015-01-01

The notion of “nuclear non-proliferation” is twofold. It refers to: (a) reduction of the number of existing arsenals (vertical non-proliferation), and (b) containment of the number of States that possess nuclear weapons, or control of non-state actors (horizontal non-proliferation). At the international law level, as vertical non-proliferation, there are bilateral or multilateral agreements that ban weapons of mass destruction in certain areas (e.g.: Nuclear–Weapon– Free Zones treaties). With respect to horizontal non-proliferation, beyond the Nuclear-Weapon-Free Zones approach, the main legal text for addressing the issue is the Treaty on the Non-Proliferation of Nuclear Weapons (NPT). For the implementation of the principles contained in the NPT, a “nuclear safeguards” system has been created, and the International Atomic Energy Agency (IAEA) has been assigned the role of the nuclear “watchdog” for the NPT. However, along with this international system of safeguards, there are regional safeguards bodies: (a) the European Atomic Energy Community (EURATOM) model is the cornerstone of non-proliferation in the EU, while (b) the Brazilian-Argentine Agency for Accounting for and Control of Nuclear Materials (ABACC) controls nuclear activities in Brazil and Argentina. Moreover, the existing nuclear weapons free-zone treaties contain safeguards provisions that are additional or complementary to IAEA safeguards. For instance, (a) the Agency for the Prohibition of Nuclear Weapons in Latin America and the Caribbean (OPANAL) works for the implementation of Tlatelolco Treaty, (b) the African Commission on Nuclear Energy relates to Pelindaba Treaty, and (c) a Consultative Committee of the Parties is appointed in the context of Raratonga Treaty. The paper aims at critically analysing the different safeguards systems adopted at the international and regional level, through the adoption of a comparative approach. (author)

AFCI Safeguards Enhancement Study: Technology Development Roadmap

Energy Technology Data Exchange (ETDEWEB)

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

2008-12-31

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

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.

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

International Nuclear Information System (INIS)

Mollah, A.S.

2010-01-01

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

Remote monitoring for international safeguards

International Nuclear Information System (INIS)

Dupree, S.A.; Sonnier, C.S.

1999-01-01

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

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.

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

Improvements for optical surveillance systems in international safeguards

International Nuclear Information System (INIS)

Richter, B.; Stein, G.; Neumann, G.; Gaertner, K.J.; Whichello, J.N.

1988-01-01

Within the next few years, a transition from film camera systems to video surveillance systems will take place in international safeguards. In order to maintain the indispensable requirements of reliability and authentication, development and tests continued under the Federal Republic of Germany Support Programme of video components for IAEA safeguards applications. The prototype of a tamper resistant TV-link was developed under Task D.12/4/. A field test of the TV-link is in preparation using a production model suitable for multiplexed TV applications. The test will utilize an Agency owned, multiplexed TV system. An evaluation of the tamper resistant TV-link is given. After a successful field trial of the prototype Solid State Video Memory (SSVM-516) under task D.14 a production model has been developed under Task D.17. Several operating modes are envisaged, depending on whether it will be used in an on-site video surveillance system or in a video review station. The concept and technical features, including an explanation of the function of the video memory, are discussed

Strengthened International Nuclear Safeguards; burdens and Effects on Nuclear Technology Development

International Nuclear Information System (INIS)

Badawy, I.

2000-01-01

The present paper deals with the recent direction of strengthening the international nuclear safeguards and the effects on the development of nuclear technology for peaceful applications. The new basic principles for strengthening the international nuclear control in the direction of undeclared nuclear activities are elaborated, and the national obligations are indicated. The burdens on the development of nuclear technology are discussed. Approaches are proposed in this work for coping with the present and future situations

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

Evaluating alternative responses to safeguards alarms

International Nuclear Information System (INIS)

Al-Ayat, R.A.; Judd, B.R.; McCord, R.K.

1982-01-01

This paper describes a quantitative approach to help evaluate and respond to safeguards alarms. These alarms may be generated internally by a facility's safeguards systems or externally by individuals claiming to have stolen special nuclear material (SNM). This approach can be used to identify the most likely cause of an alarm - theft, hoax, or error - and to evaluate alternative responses to alarms. Possible responses include conducting investigations, initiating measures to recover stolen SNM, and replying to external threats. Based on the results of each alarm investigation step, the evaluation revises the likelihoods of possible causes of an alarm, and uses this information to determine the optimal sequence of further responses. The choice of an optimal sequence of responses takes into consideration the costs and benefits of successful thefts or hoaxes. These results provide an analytical basis for setting priorities and developing contingency plans for responding to safeguards alarms

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

Energy Technology Data Exchange (ETDEWEB)

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

2014-08-08

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

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

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

International safeguards for fast critical facilities

International Nuclear Information System (INIS)

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

1978-12-01

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

Nuclear Safeguards Infrastructure Development and Integration with Safety and Security

International Nuclear Information System (INIS)

Kovacic, Donald N.; Raffo-Caiado, Ana Claudia; McClelland-Kerr, John; Van sickle, Matthew; Bissani, Mo

2009-01-01

Faced with increasing global energy demands, many developing countries are considering building their first nuclear power plant. As a country embarks upon or expands its nuclear power program, it should consider how it will address the 19 issues laid out in the International Atomic Energy Agency (IAEA) document Milestones in Development of a National Infrastructure for Nuclear Power. One of those issues specifically addresses the international nonproliferation treaties and commitments and the implementation of safeguards to prevent diversion of nuclear material from peaceful purposes to nuclear weapons. Given the many legislative, economic, financial, environmental, operational, and other considerations preoccupying their planners, it is often difficult for countries to focus on developing the core strengths needed for effective safeguards implementation. Typically, these countries either have no nuclear experience or it is limited to the operation of research reactors used for radioisotope development and scientific research. As a result, their capacity to apply safeguards and manage fuel operations for a nuclear power program is limited. This paper argues that to address the safeguards issue effectively, a holistic approach must be taken to integrate safeguards with the other IAEA issues including safety and security - sometimes referred to as the '3S' concept. Taking a holistic approach means that a country must consider safeguards within the context of its entire nuclear power program, including operations best practices, safety, and security as well as integration with its larger nonproliferation commitments. The Department of Energy/National Nuclear Security Administration's International Nuclear Safeguards and Engagement Program (INSEP) has been involved in bilateral technical cooperation programs for over 20 years to promote nonproliferation and the peaceful uses of nuclear energy. INSEP is currently spearheading efforts to promote the development of

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)

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.

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)

International seminar on safeguards information reporting and processing. Extended synopses

International Nuclear Information System (INIS)

1998-01-01

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

Gamma techniques for IAEA [International Atomic Energy Agency] safeguards at centrifuge enrichment cascades

International Nuclear Information System (INIS)

Aaldijk, J.K.; de Betue, P.A.C.; van der Meer, K.; Harry, R.J.S.

1987-01-01

On February 4, 1983, the Hexapartite Safeguards Project (HSP) concluded that the safeguards approach involving limited frequency unannounced access (LFUA) by International Atomic Energy Agency (IAEA) inspectors to cascades areas together with inspection activities outside the cascade areas meets the IAEA safeguards objectives in an effective and efficient way. In this way, the risks of revealing sensitive information were also minimized. The approach has been defined clearly and unambiguously, and it should be applied equally to all technology holders. One of the conclusions of the HSP was that a nondestructive assay go/no-go technique should be used during the LFUA inspections in the cascade areas of centrifuge enrichment plants. The purpose is to verify that the enrichment of the product UF 6 gas is in the range of low-enriched uranium (LEU), i.e., the enrichment is below 20%

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)

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

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 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

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

International seminar on safeguards information reporting and processing. Extended synopses

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-12-31

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

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)

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.

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

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

Containment and surveillance systems for international safeguards

International Nuclear Information System (INIS)

Ney, J.F.

1978-01-01

Important criteria in measuring the effectiveness of IAEA safeguards include timeliness of detection of diversion, timeliness of reporting such detections, and confidence in determining the amount of material diverted. Optimum use of IAEA inspectors, combined with adequate instrumentation, can provide a practical means for achieving these criteria. System studies are being carried out for different types of facilities that may come under IAEA safeguards to determine the proper balance between inspector's efforts and the use of safeguards instrumentation. A description of a typical study is presented. Based on the results of these studies, the program undertaken to develop those containment and surveillance subsystems for which the technical feasibility and operational acceptability need to be established is described

Safeguards-by-Design: Guidance for High Temperature Gas Reactors (HTGRs) With Pebble Fuel

Energy Technology Data Exchange (ETDEWEB)

Philip Casey Durst; Mark Schanfein

2012-08-01

The following is a guidance document from a series prepared for the U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA), under the Next Generation Safeguards Initiative (NGSI), to assist facility designers and operators in implementing international Safeguards-by-Design (SBD). SBD has two main objectives: (1) to avoid costly and time consuming redesign work or retrofits of new nuclear fuel cycle facilities and (2) to make the implementation of international safeguards more effective and efficient at such facilities. In the long term, the attainment of these goals would save industry and the International Atomic Energy Agency (IAEA) time, money, and resources and be mutually beneficial. This particular safeguards guidance document focuses on pebble fuel high temperature gas reactors (HTGR). The purpose of the IAEA safeguards system is to provide credible assurance to the international community that nuclear material and other specified items are not diverted from peaceful nuclear uses. The safeguards system consists of the IAEA’s statutory authority to establish safeguards; safeguards rights and obligations in safeguards agreements and additional protocols; and technical measures implemented pursuant to those agreements. Of foremost importance is the international safeguards agreement between the country and the IAEA, concluded pursuant to the Treaty on the Non-Proliferation of Nuclear Weapons (NPT). According to a 1992 IAEA Board of Governors decision, countries must: notify the IAEA of a decision to construct a new nuclear facility as soon as such decision is taken; provide design information on such facilities as the designs develop; and provide detailed design information based on construction plans at least 180 days prior to the start of construction, and on "as-built" designs at least 180 days before the first receipt of nuclear material. Ultimately, the design information will be captured in an IAEA Design Information

IAEA safeguards and classified materials

International Nuclear Information System (INIS)

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

1997-01-01

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

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

Internationally Safeguarded Atomic Fuel Exchange Center for the Asian Pacific Basin

International Nuclear Information System (INIS)

Selvaduray, G.; Anderson, R.N.; Goldstein, M.K.

1979-01-01

The concept of an Internationally Safeguarded Atomic Fuel Exchange Center (ISAFE) for the Asia-Pacific Basin is examined. The geography and nuclear capabilitiy of the countries that comprise the Asia-Pacific Basin is described in full length. The incentives and the limitations for the establishment of the ISAFE center in the Asia-Pacific Basin are discussed in detail. 34 refs

Introducing the Brazilian program of technical support to the International Atomic Energy Agency - Department of Safeguards

International Nuclear Information System (INIS)

Vinhas, Laercio A.; Palhares, Lilia C.; Dias, Fabio C.; Khlebnikov, Nikolai

2009-01-01

As an active Member State of the International Atomic Energy Agency (IAEA), Brazil has applied substantial resources in order to maintain the best possible cooperation with the Agency, aiming at a continuous improvement of the effectiveness and efficiency of the safeguards system. Over the last decades a number of projects, involving the participation of high-level Brazilian professionals in the nuclear area, have already been jointly completed. To continue providing this voluntary support to the IAEA Department of Safeguards for research, development and implementation, in 2006 Brazil decided to accept the IAEA's invitation to participate in the IAEA Member States Support Programmes initiative, which currently includes 21 Member States. The Research and Development (R and D) Programme for Nuclear Verification is the IAEA reference in this regard, establishing the high priority needs and describing each recognized departmental project. The Programme is issued every two years. The 'Brazilian Support Programme (BRZ SP)' was established on the basis of a set of administrative procedures titled 'Cooperation Arrangements and Guidelines', agreed between the Brazilian National Nuclear Energy Commission (CNEN) and the IAEA - Department of Safeguards. The scope of the BRZ SP includes: the participation in field tests and the evaluation of state-of-the-art technologies as requested by the IAEA for its safeguards applications; the training of safeguards personnel involved with safeguards implementation at both facility and State levels; laboratorial support in the area of destructive and nondestructive analysis of nuclear materials; the analysis of safeguards issues; information acquisition, analysis and evaluation; and the provision of human resources, such as experts and consultants to work directly with the IAEA Secretariat. The activities agreed under the BRZ SP are not restricted to CNEN staff members. Professionals from other Brazilian organizations may also be involved

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

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.

Safeguarding and Protecting the Nuclear Fuel Cycle

International Nuclear Information System (INIS)

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

2010-01-01

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

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

International legal instruments promoting synergy's in nuclear safety, security and safeguards: myth of reality?

International Nuclear Information System (INIS)

Vasmant, A.

2009-01-01

The purpose of this article is to assess the existing synergies between nuclear safety, nuclear security and non-proliferation/safeguards resulting from the adoption of international legal instruments. Keeping in mind that a synergy is the extra success achieved by two or more elements of a system working together instead of on their own, this paper will try to evaluate the possibility of a so-called '3 S' approach to optimize the benefits so defined. to achieve this, Part 1 focuses on the history of the three regimes and their major features, while Part 2, 3 and 4 explore the various benefits of, limits to, synergies between the nuclear safety, nuclear security and safeguards regimes. Part 5 describes the potential '3 S' approach in international nuclear law. (N.C.)

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

Materials management in an internationally safeguarded fuels reprocessing plant

International Nuclear Information System (INIS)

Hakkila, E.A.; Baker, A.L.; Cobb, D.D.

1980-04-01

The following appendices are included: aqueous reprocessing and conversion technology, reference facilities, process design and operating features relevant to materials accounting, operator's safeguards system structure, design principles of dynamic materials accounting systems, modeling and simulation approach, optimization of measurement control, aspects of international verification problem, security and reliability of materials measurement and accounting system, estimation of in-process inventory in solvent-extraction contactors, conventional measurement techniques, near-real-time measurement techniques, isotopic correlation techniques, instrumentation available to IAEA inspectors, and integration of materials accounting and containment and surveillance

Materials management in an internationally safeguarded fuels reprocessing plant

Energy Technology Data Exchange (ETDEWEB)

Hakkila, E.A.; Baker, A.L.; Cobb, D.D.

1980-04-01

The following appendices are included: aqueous reprocessing and conversion technology, reference facilities, process design and operating features relevant to materials accounting, operator's safeguards system structure, design principles of dynamic materials accounting systems, modeling and simulation approach, optimization of measurement control, aspects of international verification problem, security and reliability of materials measurement and accounting system, estimation of in-process inventory in solvent-extraction contactors, conventional measurement techniques, near-real-time measurement techniques, isotopic correlation techniques, instrumentation available to IAEA inspectors, and integration of materials accounting and containment and surveillance. (DLC)

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.)

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

International Nuclear Information System (INIS)

2006-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-07-01

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

From safeguards to treaty verification and the future

International Nuclear Information System (INIS)

Harry, J.

1997-01-01

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

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

Pickering safeguards: a preliminary analysis

International Nuclear Information System (INIS)

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

1977-05-01

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

Safeguards and security progress report, January-December 1985

International Nuclear Information System (INIS)

1987-03-01

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

Safeguards and security progress report, January-December 1985

Energy Technology Data Exchange (ETDEWEB)

1987-03-01

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

Safeguards technology development for spent fuel storage and disposal

International Nuclear Information System (INIS)

Sanders, K.E.

1991-01-01

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

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.

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

Framework for analyzing safeguards alarms and response decisions

International Nuclear Information System (INIS)

Al-Ayat, R.A.; Judd, B.R.; McCord, R.K.

1982-01-01

This paper describes a quantitative approach to help evaluate and respond to safeguards alarms. These alrms may be generated internally by a facility's safeguards systems or externally by individuals claiming to possess stolen Special Nuclear Material (SNM). This approach can be used to identify the most likely cause of an alarm - theft, hoax, or error - and to evaluate alternative responses to alarms. Possible responses include conducting investigations, initiating measures to recover stolen SNM, and replying to external threats. Based on the results of each alarm investigation step, the evaluation revises the likelihoods of possible causes of an alarm, and uses this information to determine the optimal sequence of further responses. The choice of an optimal sequence of responses takes into consideration the costs and benefits of successful thefts or hoaxes. These results provide an analytical basis for setting priorities and developing contingency plans for responding to safeguards alarms

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

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

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

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: Past, Present, and Future

Energy Technology Data Exchange (ETDEWEB)

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

2012-06-14

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

Development of DUPIC safeguards technology

Energy Technology Data Exchange (ETDEWEB)

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

2000-03-01

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

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.

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)

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

Energy Technology Data Exchange (ETDEWEB)

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

2009-11-01

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

Process monitoring for reprocessing plant safeguards: a summary review

International Nuclear Information System (INIS)

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

1986-10-01

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

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.

TASTEX: Tokai Advanced Safeguards Technology Exercise

International Nuclear Information System (INIS)

1982-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2012-06-15

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

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

International Nuclear Information System (INIS)

Chatelus, Renaud; )

2012-01-01

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

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)

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

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 and Security progress report, January--December 1989

Energy Technology Data Exchange (ETDEWEB)

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

1990-11-01

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

Role of near-real-time accounting in international safeguards for reprocessing plants

International Nuclear Information System (INIS)

Hakkila, E.A.; Dietz, R.J.; Shipley, J.P.

1979-01-01

The effectiveness of conventional nuclear materials accounting systems, both national and international, is constrained by the fundamental process features of high-throughput nuclear facilities and the economic limits of effective nuclear materials management consistent with production goals. Conventional accounting, complemented by near-real-time accounting, may meet projected IAEA performance goals for detecting diversion in medium- and high-throughput reprocessing facilities projected for the late 1900's. The design of materials accounting systems for international safeguards in reprocessing plants is discussed, paying particular attention to the question of international verification. Specific problems in measurement techniques, data evaluation, and systems structure are identified, and the current status of research and development efforts is reviewed

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)

Nuclear material safeguards technology development in the new structure of BATAN organization

International Nuclear Information System (INIS)

Ilyas, Zurias

2001-01-01

Full text: The implementation of Nuclear Energy Act No. 10/97 has led to a restructuring in BATAN organization in July 1999. A new unit, Center for Nuclear Material Safeguards Technology (PTPBN), was established to be especially in charge of safeguards facilities. The main responsibility of this unit is to develop the technology of safeguards and physical protection. The function of this unit is also to analyze the operational technical aspect of the International Convention of Nuclear. The duties of Center for Nuclear Material Safeguards Technology can be seen from the various programs set up for every fiscal year. The programs for the year 2000 were: Analyses of SSAC implementation in BATAN; Development of Safeguards information system; Creation of database of physical protection technology; Physical protection simulator for Bandung reactor research; Development of detector technology for physical protection system; Identification of BATAN activities and facilities submitted to IAEA in order to be in line with the Additional Protocol to the agreement between the Republic of Indonesia and the International Atomic Energy Agency for the Application of Safeguards in connection with the Treaty on Non-Proliferation on Nuclear Weapons, which was ratified on September 29th, 1999 in Vienna, Austria; Seminar on Safeguards technology held in Jakarta in September 2000. The program of 2001 will be focusing on the continuation of the previous year's program as well as the creation of new ones, such as: Collaboration with other countries. At initial stage experts from JBC-Japan were invited to share their expertise on their safeguards information system; Development of education and training for safeguards operators by emphasizing more on the techniques of nuclear materials measurement; Seminar on Safeguards technology scheduled for December 2001 by inviting experts from IAEA and modem countries; Field survey to determine the location of radionuclide station in Indonesia in

Outcome and Perspectives from the First IAEA International Technical Meeting on Statistical Methodologies for Safeguards

International Nuclear Information System (INIS)

Norman, C.; Binner, R.; Peter, N. J.; Wuester, J.; Zhao, K.; Krieger, T.; Walczak-Typke, A.C.; Richet, S.; Portaix, C.G.; Martin, K.; Bonner, E.R.

2015-01-01

Statistical and probabilistic methodologies have always played a fundamental role in the field of safeguards. In-field inspection approaches are based on sampling algorithms and random verification schemes designed to achieve a designed detection probability for defects of interest (e.g., missing material, indicators of tampering with containment and other equipment, changes of design). In addition, the evaluation of verification data with a view to drawing soundly based safeguards conclusions rests on the application of various advanced statistical methodologies. The considerable progress of information technology in the field of data processing and computational capabilities as well as the evolution of safeguards concepts and the steep increase in the volume of verification data in the last decades call for the review and modernization of safeguards statistical methodologies, not only to improve the efficiency of the analytical processes but also to address new statistical and probabilistic questions. Modern computer-intensive approaches are also needed to fully exploit the large body of verification data collected over the years in the increasing number and diversifying types of nuclear fuel cycle facilities in the world. The first biennial IAEA International Technical Meeting on Statistical Methodologies for Safeguards was held in Vienna from the 16 to 18 October 2013. Recommendations and a working plan were drafted which identify and chart necessary steps to review, harmonize, update and consolidate statistical methodologies for safeguards. Three major problem spaces were identified: Random Verification Schemes, Estimation of Uncertainties and Statistical Evaluation of Safeguards Verification Data for which a detailed list of objectives and actions to be taken were established. Since the meeting, considerable progress was made to meet these objectives. The actions undertaken and their outcome are presented in this paper. (author)

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)

Prospects for regional safeguards systems - State-level Approach

International Nuclear Information System (INIS)

Peixoto, O.J.M.

2013-01-01

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

Zone approaches to international safeguards of a nuclear fuel cycle

International Nuclear Information System (INIS)

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

1986-01-01

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

IAEA safeguards: some pros and cons

International Nuclear Information System (INIS)

Kelly, P.

1986-01-01

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

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

Survey of special nuclear material vehicle monitors for domestic and international safeguards

International Nuclear Information System (INIS)

Fehlau, P.E.; Atwater, H.F.; Caldwell, J.T.; Shunk, E.R.

1979-01-01

Special nuclear materials vehicle monitors, including gateside vehicle monitors, hand-held personnel-vehicle monitors, and a new tunnel monitor concept for very large vehicles, are discussed. The results of a comparison of effectiveness of monitors for domestic application are presented. The results of calculations and small scale prototype measurements are given for a tunnel-like neutron monitor for monitoring at the perimeter of an enrichment plant subjected to 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.

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

Improved verification methods for safeguards verifications at enrichment plants

International Nuclear Information System (INIS)

Lebrun, A.; Kane, S. C.; Bourva, L.; Poirier, S.; Loghin, N. E.; Langlands, D.

2009-01-01

The International Atomic Energy Agency (IAEA) has initiated a coordinated research and development programme to improve its verification methods and equipment applicable to enrichment plants. The programme entails several individual projects to meet the objectives of the IAEA Safeguards Model Approach for Gas Centrifuge Enrichment Plants updated in 2006. Upgrades of verification methods to confirm the absence of HEU (highly enriched uranium) production have been initiated and, in particular, the Cascade Header Enrichment Monitor (CHEM) has been redesigned to reduce its weight and incorporate an electrically cooled germanium detector. Such detectors are also introduced to improve the attended verification of UF 6 cylinders for the verification of the material balance. Data sharing of authenticated operator weighing systems such as accountancy scales and process load cells is also investigated as a cost efficient and an effective safeguards measure combined with unannounced inspections, surveillance and non-destructive assay (NDA) measurement. (authors)

Improved verification methods for safeguards verifications at enrichment plants

Energy Technology Data Exchange (ETDEWEB)

Lebrun, A.; Kane, S. C.; Bourva, L.; Poirier, S.; Loghin, N. E.; Langlands, D. [Department of Safeguards, International Atomic Energy Agency, Wagramer Strasse 5, A1400 Vienna (Austria)

2009-07-01

The International Atomic Energy Agency (IAEA) has initiated a coordinated research and development programme to improve its verification methods and equipment applicable to enrichment plants. The programme entails several individual projects to meet the objectives of the IAEA Safeguards Model Approach for Gas Centrifuge Enrichment Plants updated in 2006. Upgrades of verification methods to confirm the absence of HEU (highly enriched uranium) production have been initiated and, in particular, the Cascade Header Enrichment Monitor (CHEM) has been redesigned to reduce its weight and incorporate an electrically cooled germanium detector. Such detectors are also introduced to improve the attended verification of UF{sub 6} cylinders for the verification of the material balance. Data sharing of authenticated operator weighing systems such as accountancy scales and process load cells is also investigated as a cost efficient and an effective safeguards measure combined with unannounced inspections, surveillance and non-destructive assay (NDA) measurement. (authors)

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

Safeguards Culture: Analogies from Safety Culture and Security Culture

International Nuclear Information System (INIS)

Naito, K.

2013-01-01

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

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

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

Research on seal control systems for international nuclear safeguard and the vulnerability assessment on the seals

International Nuclear Information System (INIS)

Zhang Hongjian; Liu Tianshu; Cao Fangfang; Xu Chunyan

2014-01-01

Safeguard seals, also called Tamper-indicating devices (TIDs), are widely used to detect tampering or unauthorized entry in the international safeguard and security systems, Seal control systems consist of seal implementing plan, seal development and the vulnerability assessment on tbe seals, effective implementing procedures and methods of the seals. The vulnerability assessment contents of safeguard seals, thermo-shrinked film seals being as an example, and seals control systems in the implementation program are researched. The seal control systems discuss task assignment, seals management flow and seals program data flow to promote applying effectively seals. The vulnerability assessment program of seals studies assurance level to some different tampering techniques and measures. The researches must promote utilizing seals effectively for nuclear security, non-proliferation of nuclear weapons, radioactive waste management, and the nuclear material accounting and control. (authors)

Safeguards and physics measurements

International Nuclear Information System (INIS)

Carchon, R.

2002-01-01

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

Safeguards and legal matters 1996. International Atomic Energy Agency publications

International Nuclear Information System (INIS)

1997-03-01

This catalogue lists all currently valid sales publications of the International Atomic Energy Agency dealing with Safeguards and Legal Matters. Most publications are published in English. Proceedings of conferences, symposia and panels of experts may contain some papers in languages other than English (French, Russian or Spanish), but all of these papers have abstracts in English. It should be noted that prices of books are quoted in Austrian Schillings. The prices do not include local taxes and are subject to change without notice. All books in this catalogue are 16 x 24 cm, paper-bound, unless otherwise stated

International Target Values 2010 for Measurement Uncertainties in Safeguarding Nuclear Materials

Energy Technology Data Exchange (ETDEWEB)

Zhao, M.; Penkin, M.; Norman, C.; Balsley, S. [IAEA, Vienna (Australia); others, and

2012-12-15

This issue of the International Target Values (ITVs) represents the sixth revision, following the first release of such tables issued in 1979 by the ESARDA/WGDA. The ITVs are uncertainties to be considered in judging the reliability of analytical techniques applied to industrial nuclear and fissile material, which are subject to safeguards verification. The tabulated values represent estimates of the 'state of the practice' which should be achievable under routine measurement conditions. The most recent standard conventions in representing uncertainty have been considered, while maintaining a format that allows comparison with the previous releases of the ITVs. The present report explains why target values are needed, how the concept evolved and how they relate to the operator's and inspector's measurement systems. The ITVs-2010 are intended to be used by plant operators and safeguards organizations, as a reference of the quality of measurements achievable in nuclear material accountancy, and for planning purposes. The report suggests that the use of ITVs can be beneficial for statistical inferences regarding the significance of operator-inspector differences whenever valid performance values are not available.

Remote monitoring: A global partnership for safeguards

International Nuclear Information System (INIS)

Bardsley, J.

1996-01-01

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

MC ampersand A policy issues for international inspections at DOE nuclear facilities

International Nuclear Information System (INIS)

Crawford, D.W.; Zack, N.R.

1994-01-01

Recent initiatives and executive decisions within the US have included an offer to place certain special nuclear materials from the former weapons stockpile under international safeguards inspections. The nuclear materials at issue are excess materials; other materials characterized as strategic reserve will not be subject to these international activities. Current Department of Energy requirements and procedures to account for and control these nuclear materials may need to be modified to accommodate these inspections. Safeguards issues, such as physical inventory frequency and verification requirements, may rise from the collateral safeguards activities in support of both domestic and international safeguards. This paper will discuss Office of Safeguards and Security policy and views on these international inspection activities at former nuclear weapons facilities, including implications for current domestic safeguards approaches currently implemented at these facilities

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

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

International safeguards at the feed and withdrawal area of a gas centrifuge uranium enrichment plant

International Nuclear Information System (INIS)

Gordon, D.M.; Sanborn, J.B.

1980-01-01

This paper discusses the application of International Atomic Energy Agency (IAEA) safeguards at a model gas centrifuge uranium enrichment plant designed for the production of low-enriched uranium; particular emphasis is placed upon the verification by the IAEA of the facility material balance accounting. 13 refs

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)

Safeguards and physics measurements

Energy Technology Data Exchange (ETDEWEB)

Carchon, R

2002-04-01

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

Safeguards for geological repositories

International Nuclear Information System (INIS)

Fattah, A.

2000-01-01

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

Survey of nuclear safeguards in the European Community

International Nuclear Information System (INIS)

Gmelin, W.

1992-01-01

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

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.

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

International Nuclear Information System (INIS)

PEPPER, S.; OSIECKI, C.

2006-01-01

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

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).

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 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

The state-level approach: moving beyond integrated safeguards

International Nuclear Information System (INIS)

Tape, James W.

2008-01-01

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

Technology development of nuclear material safeguards for DUPIC fuel cycle

Energy Technology Data Exchange (ETDEWEB)

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

1997-07-01

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

Designing and Operating for Safeguards: Lessons Learned From the Rokkasho Reprocessing Plant (RRP)

International Nuclear Information System (INIS)

Johnson, Shirley J.; Ehinger, Michael

2010-01-01

This paper will address the lessons learned during the implementation of International Atomic Energy Agency (IAEA) safeguards at the Rokkasho Reprocessing Plant (RRP) which are relevant to the issue of 'safeguards by design'. However, those lessons are a result of a cumulative history of international safeguards experiences starting with the West Valley reprocessing plant in 1969, continuing with the Barnwell plant, and then with the implementation of international safeguards at WAK in Germany and TRP in Japan. The design and implementation of safeguards at RRP in Japan is the latest and most challenging that the IAEA has faced. This paper will discuss the work leading up to the development of a safeguards approach, the design and operating features that were introduced to improve or aid in implementing the safeguards approach, and the resulting recommendations for future facilities. It will provide an overview of how 'safeguardability' was introduced into RRP.

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

Zone approaches to international safeguards of a nuclear fuel cycle

International Nuclear Information System (INIS)

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

1986-01-01

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

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

International Nuclear Information System (INIS)

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

2008-01-01

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

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)

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

Legal instruments related to the application of safeguards

International Nuclear Information System (INIS)

Rames, J.

1999-01-01

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

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

International Nuclear Information System (INIS)

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

2009-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2009-01-01

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

The remote monitoring systems LOVER and RECOVER for international safeguards technical, economic and legal aspects

International Nuclear Information System (INIS)

Lauppe, W.D.; Stein, G.; Rezniczek, A.; Stienen, U.

1983-12-01

The electronic remote monitoring systems RECOVER and LOVER were developed to comply with the IAEA's tasks concerning international nuclear materials safeguards with the aim of reducing the inspection expenditure and enhancing control effectiveness. The present study on the technical, economic and legal aspects of an application of these systems is intended to show possible implications and provide argumentation aids for discussions on the application of these systems. RECOVER and LOVER offer the possibility of establishing a direct communication path between containment and surveillance system (c/s), instruments at the site of application and a central monitoring station. The demonstration versions of both systems have shown that remote interrogation of data under safeguards-specific boundary conditions (e.g. requirement of tamper safety) will be technically feasible. (orig./HP)

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.

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

International Nuclear Information System (INIS)

Howlett, Darryl.

1988-08-01

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

The third review conference of the parties of the Treaty on Non-Proliferation of Nuclear Weapons, and recent developments concerning international safeguards

International Nuclear Information System (INIS)

Canty, M.J.; Richter, B.; Schlupp, C.; Stein, G.

1986-11-01

The non-proliferation activities and instruments are listed in a table. The two main instruments are the Non-Proliferation Treaty and the IAEA Safeguards, which are supplemented by treaties of regional restricted effects, such as the Treaty of Tlatelolco and the EURATOM treaty. The two-tier structure of the treaties, i.e. to provide for non-proliferation of nuclear weapons and at the same time foster the peaceful uses of nuclear energy, has proven to have a particularly stabilizing effect, which was confirmed by the last Review Conference of the Parties to the Treaty on Non-Proliferation. The conference members were particularly satisfied with the results of the IAEA Safeguards. Future developments towards improving international safeguards will concentrate on operator-friendly and financially reasonable safeguards measures, such as safeguards effectiveness evaluations and near-real-time accountancy. The results of the CAS discussions on the definition of principles and goals of co-operation for the peaceful uses of nuclear energy are of importance also to the PUNE conference. The PUNE conference will be held in 1987 and is expected to yield points of orientation for further embedding the non-proliferation principle in the international co-operative activities and the nuclear business in the 1980s. (orig./HP) [de

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

Energy Technology Data Exchange (ETDEWEB)

Sapir, J.L. (comp.)

1977-06-01

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

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

International Nuclear Information System (INIS)

Sapir, J.L.

1977-06-01

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

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

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

International safeguards without material balance areas

International Nuclear Information System (INIS)

Sanborn, J.B.; Lu Mingshih; Indusi, J.P.

1992-01-01

Recently altered perceptions of the role of the non-proliferation regime, as well as continued IAEA funding constraints, suggest a need to re-examine the fundamentals of IAEA verification strategy. This paper suggests that abandoning certain material balance area (MBA) related concepts that nominally form the basic framework of ''full-scope'' safeguards would result in a more flexible inspection regime. The MBA concept applied in the domestic context enables a national authority to localize losses in space and in time and to minimize the need to measure in-process inventory. However, these advantages do not accrue to an international verification regime because it cannot truly verify the ''flows'' between MBAs without extensive containment/surveillance measures. In the verification model studied, the entire nuclear inventory of a state is periodically declared and verified simultaneously in one or two large segments (containing possibly many MBAS). Simultaneous inventory of all MBAs within a segment would occur through advance ''mailbox'' declarations and random selection of MBAs for on-site verification or through enhanced containment/surveillance techniques. Flows are generally speaking not verified. This scheme would free the inspectorate from the obligation to attempt to verify on-site each stratum of the material balance of every facility declaring significant quantities of nuclear material

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

Technical bases for OCRWM's [Office of Civilian Radioactive Waste Management] policy decisions on international safeguards

International Nuclear Information System (INIS)

Sprecher, W.M.

1989-01-01

The purpose of this paper is to discuss the technical factors that contributed to the formulation of the international safeguards policy enunciated in September 1988 by the U.S. Department of Energy's (DOE's) Office of Civilian Radioactive Waste Management (OCRWM), which is the federal organization responsible for the implementation of the Nuclear Waste Policy Act of 1982, as amended

Safeguards and security research and development progress report, October 1993--September 1994

Energy Technology Data Exchange (ETDEWEB)

Smith, D.B.; Jaramillo, G.R. [comp.

1995-08-01

This report describes the activities carried out by the Los Alamos Safeguards and Security Research and Development (R&D) program from October 1993 through September 1994. The activities presented in the first part of the report were directed primarily to domestic US safeguards applications and were, for the most part, sponsored by the Department of Energy`s Office of Safeguards and Security (DOE/OSS, NN-50). The activities described in Part 2, International Safeguards, were supported by the International Safeguards Division of the Office of Arms Control and Nonproliferation (DOE/OACN, NN-40). Part 3 describes several safeguards or safeguards-related activities that have other sponsors. The final part of the report lists titles and abstracts of Los Alamos safeguards R&D reports, technical journal articles, and conference papers that were published or presented in 1994.

Safeguards and security research and development progress report, October 1993--September 1994

International Nuclear Information System (INIS)

Smith, D.B.; Jaramillo, G.R.

1995-08-01

This report describes the activities carried out by the Los Alamos Safeguards and Security Research and Development (R ampersand D) program from October 1993 through September 1994. The activities presented in the first part of the report were directed primarily to domestic US safeguards applications and were, for the most part, sponsored by the Department of Energy's Office of Safeguards and Security (DOE/OSS, NN-50). The activities described in Part 2, International Safeguards, were supported by the International Safeguards Division of the Office of Arms Control and Nonproliferation (DOE/OACN, NN-40). Part 3 describes several safeguards or safeguards-related activities that have other sponsors. The final part of the report lists titles and abstracts of Los Alamos safeguards R ampersand D reports, technical journal articles, and conference papers that were published or presented in 1994

Designing and Operating for Safeguards: Lessons Learned From the Rokkasho Reprocessing Plant (RRP)

Energy Technology Data Exchange (ETDEWEB)

Johnson, Shirley J.; Ehinger, Michael

2010-08-07

This paper will address the lessons learned during the implementation of International Atomic Energy Agency (IAEA) safeguards at the Rokkasho Reprocessing Plant (RRP) which are relevant to the issue of ‘safeguards by design’. However, those lessons are a result of a cumulative history of international safeguards experiences starting with the West Valley reprocessing plant in 1969, continuing with the Barnwell plant, and then with the implementation of international safeguards at WAK in Germany and TRP in Japan. The design and implementation of safeguards at RRP in Japan is the latest and most challenging that the IAEA has faced. This paper will discuss the work leading up to the development of a safeguards approach, the design and operating features that were introduced to improve or aid in implementing the safeguards approach, and the resulting recommendations for future facilities. It will provide an overview of how ‘safeguardability’ was introduced into RRP.

Legal instruments related to the application of safeguards

International Nuclear Information System (INIS)

Rockwood, Laura

2001-01-01

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

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.

Agreement reached on integrated safeguards in European Union

International Nuclear Information System (INIS)

2010-01-01

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

Safeguard Verification as Cooperative Measure for Non Proliferation Control in Peru

International Nuclear Information System (INIS)

Ramirez, R.

2010-01-01

Peru applies the safeguard measures on its nuclear activities based in the International Atomic Energy Agency (IAEA) Safeguard Agreement and the Additional Protocol which has been fully implemented becoming part of the Integrated Safeguard since 2005. In addition to international safeguard commitments Peru is also committed with the United Nations 1540 Resolution by which national controls has to be established for preventing the proliferation of mass destruction weapons and their vector systems. The safeguards measures have become an important part of the verification activities related to this Resolution by analyzing of materials and equipment to be imported or that may be in transit across the country. These activities are part of those developed jointly with other governmental organizations. (author)

Select Generic Dry-Storage Pilot Plant Design for Safeguards and Security by Design (SSBD) per Used Fuel Campaign

Energy Technology Data Exchange (ETDEWEB)

Demuth, Scott Francis [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Sprinkle, James K. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-05-26

As preparation to the year-end deliverable (Provide SSBD Best Practices for Generic Dry-Storage Pilot Scale Plant) for the Work Package (FT-15LA040501–Safeguards and Security by Design for Extended Dry Storage), the initial step was to select a generic dry-storage pilot plant design for SSBD. To be consistent with other DOE-NE Fuel Cycle Research and Development (FCR&D) activities, the Used Fuel Campaign was engaged for the selection of a design for this deliverable. For the work Package FT-15LA040501–“Safeguards and Security by Design for Extended Dry Storage”, SSBD will be initiated for the Generic Dry-Storage Pilot Scale Plant described by the layout of Reference 2. SSBD will consider aspects of the design that are impacted by domestic material control and accounting (MC&A), domestic security, and international safeguards.

Safeguards can not operate alone

International Nuclear Information System (INIS)

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

2013-01-01

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

Addressing verification challenges, 16 October 2006, Vienna, Austria, Symposium on International Safeguards (16-20 October 2006)

International Nuclear Information System (INIS)

ElBaradei, M.

2006-01-01

In his talk about Verification Challenges Dr. Mohamed ElBaradei, Director General of the IAEA, welcomed the participants of the Symposium on International Safeguards. He stated that safeguards is probably the most difficult task entrusted to an international organization and that a major increase in nuclear energy around the globe is expected which means that nuclear know-how is spread to more and more countries and can be applied to both peaceful purposes and also non-peaceful purposes. More and more countries want to go in for the nuclear fuel cycle including sensitive fuel cycle activities like enrichment and reprocessing, they become so-called 'virtual nuclear weapons States. There is the need to develop a new international or multinational approach to the fuel cycle so as to avoid ending up with not just nine nuclear weapon States but another 20 or 30 States which have the capacity to develop nuclear weapons in a very short span of time. He stressed the important linkage between disarmament and non-proliferation and remembered the audience that safeguards, although very much a technical activity, operates in a politically charged environment. The IAEA's job is to make sure that countries with comprehensive safeguards are conducting all their activities exclusively for peaceful purposes. The ability to discover possible undeclared activities is a key challenge the IAEA is facing. He mentioned that the IAEA does not get all the information they would need, for example the IAEA does not get systematic information from the Nuclear Suppliers Group on exports and imports. Without the Additional Protocol the IAEA is also hampered in its ability to detect undeclared activities, e.g in the R and D activities that do not directly involve nuclear material. Another key issue are financial resources. Transparency measures in certain situations are under considerations including interviewing people, having access to documents, things that are not strictly required by the

Verification and the safeguards legacy

International Nuclear Information System (INIS)

Perricos, Demetrius

2001-01-01

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

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.)

National and International Security Applications of Cryogenic Detectors - Mostly Nuclear Safeguards

International Nuclear Information System (INIS)

Rabin, Michael W.

2009-01-01

As with science, so with security--in both arenas, the extraordinary sensitivity of cryogenic sensors enables high-confidence detection and high-precision measurement even of the faintest signals. Science applications are more mature, but several national and international security applications have been identified where cryogenic detectors have high potential payoff. International safeguards and nuclear forensics are areas needing new technology and methods to boost speed, sensitivity, precision and accuracy. Successfully applied, improved nuclear materials analysis will help constrain nuclear materials diversion pathways and contribute to treaty verification. Cryogenic microcalorimeter detectors for X-ray, gamma-ray, neutron, and alpha-particle spectrometry are under development with these aims in mind. In each case the unsurpassed energy resolution of microcalorimeters reveals previously invisible spectral features of nuclear materials. Preliminary results of quantitative analysis indicate substantial improvements are still possible, but significant work will be required to fully understand the ultimate performance limits.

National and International Security Applications of Cryogenic Detectors—Mostly Nuclear Safeguards

Science.gov (United States)

Rabin, Michael W.

2009-12-01

As with science, so with security—in both arenas, the extraordinary sensitivity of cryogenic sensors enables high-confidence detection and high-precision measurement even of the faintest signals. Science applications are more mature, but several national and international security applications have been identified where cryogenic detectors have high potential payoff. International safeguards and nuclear forensics are areas needing new technology and methods to boost speed, sensitivity, precision and accuracy. Successfully applied, improved nuclear materials analysis will help constrain nuclear materials diversion pathways and contribute to treaty verification. Cryogenic microcalorimeter detectors for X-ray, gamma-ray, neutron, and alpha-particle spectrometry are under development with these aims in mind. In each case the unsurpassed energy resolution of microcalorimeters reveals previously invisible spectral features of nuclear materials. Preliminary results of quantitative analysis indicate substantial improvements are still possible, but significant work will be required to fully understand the ultimate performance limits.

International and national security applications of cryogenic detectors - mostly nuclear safeguards

International Nuclear Information System (INIS)

Rabin, Michael W.

2009-01-01

As with science, so with security - in both arenas, the extraordinary sensitivity of cryogenic sensors enables high-confidence detection and high-precision measurement even of the faintest signals. Science applications are more mature, but several national and international security applications have been identified where cryogenic detectors have high potential payoff. International safeguards and nuclear forensics are areas needing new technology and methods to boost speed, sensitivity, precision and accuracy. Successfully applied, improved nuclear materials analysis will help constrain nuclear materials diversion pathways and contribute to treaty verification. Cryogenic microcalorimeter detectors for X-ray, gamma ray, neutron, and alpha particle spectrometry are under development with these aims in mind. In each case the unsurpassed energy resolution of microcalorimeters reveals previously invi sible spectral features of nuclear materials. Preliminary results of quantitative analysis indicate substantial improvements are still possible, but significant work will be required to fully understand the ultimate performance limits.

Safeguards and Security Research and Development progress report, October 1990--September 1991

International Nuclear Information System (INIS)

Smith, D.B.; Jaramillo, G.R.

1992-07-01

This report describes the activities carried out by the Los Alamos Safeguards and Security Research And Development (R ampersand D) program from October 1990 through September 1991. The activities presented in the first three parts--Science and Technology Base Development, Basic Systems Design, and Onsite Test and Evaluation and Facility Support--were, for the most part, sponsored by the Department of Energy's Office of Safeguards and Security (DOE/OSS). The activities described in Part 4--International Safeguards--were supported by the International Safeguards Division of the Office of Arms Control and Nonproliferation (OACN/IS). Part 5 describes several safeguards or safeguards-related activities that have sponsors other than the DOE/OSS or OACN/IS. The final part of the report lists titles and abstracts of Los Alamos safeguards R ampersand D reports, technical journal articles, and conference papers that were published in 1991

Safeguardability of the vitrification option for disposal of plutonium

Energy Technology Data Exchange (ETDEWEB)

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

1996-05-01

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

Nuclear safeguards technology 1986

International Nuclear Information System (INIS)

1987-01-01

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

IAEA 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

Safeguardability of a commercial-scaled ACP facility

Energy Technology Data Exchange (ETDEWEB)

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

2004-07-01

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

Safeguardability of a commercial-scaled ACP facility

International Nuclear Information System (INIS)

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

2004-07-01

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

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

International safeguards data management system. System description: Version 1.1.; Release PLI 82

International Nuclear Information System (INIS)

Argentesi, T.; Casilli, T.; Costantini, L.; Dondi, M.G.; Franklin, M.

1982-01-01

This document describes a nuclear material accountancy system which has been developed using the ADABAS data base management system and is implemented on the JRC-Ispra computer. Throughout the report, the data base system is referred to as ''ISADAM'', i.e. International Safeguards Data Management System. The system provides tools for a safeguards authority to decide whether an operators MUF (Material Unaccounted For) can be accounted for as an accumulation of operator measurement errors. The principle objective of the applications programs described here is to provide a variance analysis of MUF in which the variance of MUF is computed as a function of the accounting declarations and the error characteristics of the operator measurement system. A overview of ISADAM is presented; then, a detailed description of the processing applied by the system is given. A description of the parameter information required by the four autonomous programs ISADAM is presented. In developing ISADAM, one of the prime factors taken into consideration was the ease with which it could be used

Paying tribute to 25 years of safeguards leadership

International Nuclear Information System (INIS)

1994-01-01

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

New evolution of safeguards and non-proliferation

International Nuclear Information System (INIS)

Seyama, K.; Kurihara, H.

1999-01-01

Since the end of the Cold War, circumstances concerning international safeguards and nuclear non-proliferation have changed drastically. At this stage, early introduction of a strengthened and streamlined new safeguards system and broad implementation of the verification activities regarding nuclear material from dismantled nuclear weapons are expected, and in the near future, the international community is expected to establish a verification regime under the Cut Off Treaty. From now on, the roles of the IAEA will become more important in these new areas. At the same time the efficiency of the activities is essential from a financial and human resources aspect in order to introduce those measures smoothly. On the other hand, the Member States should cooperate with the IAEA to improve the transparency of its nuclear policy and activities. Taking account of such circumstances, first, the authors will explain the non-proliferation policy of Japan. Second, the authors will introduce the present status of Japan's safeguards system and activities. Finally, the authors will present several tasks which are important for the IAEA and Japanese safeguards for coming several years. (author)

Advancement of safeguards inspection technology for CANDU nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

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

1999-04-01

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

Peaceful nuclear development and the three 'S' ('Safety', 'Security' and 'Safeguards')

International Nuclear Information System (INIS)

Julio Gonzalez, Abel; Abel Gonzalez, Martin

2010-01-01

We should agree on a comprehensive solution for a commensurate international control of both nuclear and radioactive material designed to ensure that peaceful nuclear developments will not cause harm to humanity. The concept of an international security system is clouded by the confusing semantics of its parts: the English concepts 'safeguards', 'safety' and 'security', on one hand, and nuclear and radioactive materials on the other hand. The objectives should be: to ensure, through appropriate safeguards, that nuclear materials are not diverted to non-peaceful activities; to prevent, through appropriate security, the unauthorized possession or use, illegal or malicious, of nuclear and radioactive materials; and, to ensure, through appropriate safety, that the use of nuclear and radioactive material will not cause harm to people and the environment. Security must be understood as an integral part of safeguards and safety, because materials that are secure are not necessarily safeguarded or safe, and materials may not be safeguarded or safe unless they are secure. Security is a necessary but not sufficient condition for safeguards and safety; security is an important but subsidiary condition of safeguards and safety; security is necessary but not sufficient to ensure nuclear control via safeguards and safety. In conclusion an International Treaty for the Control ('safeguards', 'safety' and 'security') of the Peaceful Development of Nuclear Energy and its Byproducts is proposed. It should clearly regulate the obligations and (non-compliance) penalties of the Parties, and, based on existing agreements, should be clear, logical, rational, fundamental, methodical, systematic, universal, equitable, impartial, fair and non discriminatory. (author)

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

International Nuclear Information System (INIS)

Bjornard, T.; Casey Durst, P.

2013-01-01

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

Safeguards at NRC licensed facilities: Are we doing enough

International Nuclear Information System (INIS)

Asselstine, J.K.

1986-01-01

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

The emergence of internet-based virtual private networks in international safeguards

International Nuclear Information System (INIS)

Smartt, Heidi Anne

2001-01-01

Full text: The costs associated with secure data transmission can be an obstacle to International Safeguards. Typical communication methods are priced by distance and may include telephone lines, frame relay, and ISDN. It is therefore costly to communicate globally. The growth of the Internet has provided an extensive backbone for global communications; however, the Internet does not provide intrinsic security measures. Combining the Internet with Virtual Private Network technology, which encrypts and authenticates data, creates a secure and potentially cost-effective data transmission path, as well as achieving other benefits such as reliability and scalability. Access to the Internet can be achieved by connecting to a local Internet Service Provider, which can be preferable to installing a static link between two distant points. The cost-effectiveness of the Internet-based Virtual Private Network is dependent on such factors as data amount, current operational costs, and the specifics of the Internet connection, such as user proximity to an Internet Service Provider or existing access to the Internet. This paper will introduce Virtual Private Network technology, the benefits of Internet communication, and the emergence of Internet-based Virtual Private Networks throughout the International Safeguards community. Specific projects to be discussed include: The completed demonstration of secure remote monitoring data transfer via the Internet between STUK in Helsinki, Finland, and the IAEA in Vienna, Austria; The demonstration of secure remote access to IAEA resources by traveling inspectors with Virtual Private Network software loaded on laptops; The proposed Action Sheets between ABACC/DOE and ARN/DOE, which will provide a link between Rio de Janeiro and Buenos Aires; The proposed use at the HIFAR research reactor, located in Australia, to provide remote monitoring data to the IAEA; The use of Virtual Private Networks by JRC, Ispra, Italy. (author)

Safeguards Envelope Progress FY08

Energy Technology Data Exchange (ETDEWEB)

Robert Bean; Richard Metcalf; Aaron Bevill

2008-09-01

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

Safeguards Envelope Progress FY08

International Nuclear Information System (INIS)

Bean, Robert; Metcalf, Richard; Bevill, Aaron

2008-01-01

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

Safeguards at NRC licensed facilities: Are we doing enough

International Nuclear Information System (INIS)

Asselstine, J.K.

1986-01-01

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

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

Determination of plutonium in highly radioactive liquid waste by spectrophotometry using neodymium as an internal standard for safeguards analysis. Japan support program for agency safeguards (JASPAS) JC-19

International Nuclear Information System (INIS)

Taguchi, Shigeo; Surugaya, Naoki; Sato, Soichi; Kurosawa, Akira; Watahiki, Masaru; Hiyama, Toshiaki

2006-06-01

A spectrophotometric determination using neodymium as an internal standard was developed for safeguards verification analysis of plutonium in highly radioactive liquid waste which is produced by the reprocessing of spent nuclear fuel. The internal standard is used as a means to analyze plutonium and also to authenticate the instrument conditions. The method offers reduced sample preparation and analysis time compared to isotope dilution mass spectrometry. The sample was mixed with a known amount of internal standard. Subsequently, plutonium was quantitatively oxidized to Pu(VI) by the addition of Ce(IV) for spectrophotometry. Plutonium concentration was calculated from a relation between Nd(III)/Pu(VI) molar extinction coefficient ratio and their absorbance ratio. The relative expanded uncertainty of the repeated analysis (n=5) was 8.9% (coverage factor k=2) for a highly radioactive liquid waste sample (173 mg L -1 ). The determination limit was 6 mg L -1 (ten fold's the standard deviation). This method was validated through comparison experiments with isotope dilution mass spectrometry. The analytical results of plutonium in highly radioactive liquid waste using this method were agree well with values obtained using isotope dilution mass spectrometry. The proposed method can be applied to independent on-site safeguards analysis at the Tokai Reprocessing Plant. (author)

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

The UK safeguards R and D support program

International Nuclear Information System (INIS)

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

1991-01-01

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

DOE spent nuclear fuel -- Nuclear criticality safety challenges and safeguards initiatives

International Nuclear Information System (INIS)

Hopper, C.M.

1994-01-01

The field of nuclear criticality safety is confronted with growing technical challenges and the need for forward-thinking initiatives to address and resolve issues surrounding economic, safe and secure packaging, transport, interim storage, and long-term disposal of spent nuclear fuel. These challenges are reflected in multiparameter problems involving optimization of packaging designs for maximizing the density of material per package while ensuring subcriticality and safety under variable normal and hypothetical transport and storage conditions and for minimizing costs. Historic and recently revealed uncertainties in basic data used for performing nuclear subcriticality evaluations and safety analyses highlight the need to be vigilant in assessing the validity and range of applicability of calculational evaluations that represent extrapolations from ''benchmark'' data. Examples of these uncertainties are provided. Additionally, uncertainties resulting from the safeguarding of various forms of fissionable materials in transit and storage are discussed

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

The present status of IAEA safeguards on nuclear fuel cycle facilities

International Nuclear Information System (INIS)

1979-02-01

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

Comments on fuel cycle concepts and impacts on nonproliferation and safeguards concerns

International Nuclear Information System (INIS)

Persiani, P.J.

1997-01-01

Fuel cycle technologies have inherently differing levels of proliferation risk profiles. Institutional and/or multi-national arrangements have been effective in reducing the proliferation risk concerns. The implementation of international safeguards further reduces the proliferation risk concerns by the timely detection of a possible physical diversion of SNM from fuel cycle facilities. Fuel cycles are safeguardable, but the proliferation risk characteristics of fuel cycles concepts differ significantly with consequent impacts on the international level of technical safeguards measures. The paper comments on proliferation characteristics of some of the fuel cycle concepts for the purpose of exploring development of advanced nonproliferation and safeguards measures

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.

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.

Modeling and Simulation for Safeguards and Nonproliferation Workshop

Energy Technology Data Exchange (ETDEWEB)

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

2015-01-01

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

International safeguards for a light-water reactor fuels reprocessing plant: containment and surveillance concepts

International Nuclear Information System (INIS)

Cameron, C.P.; Bleck, M.E.

1980-12-01

Concepts for containment/surveillance for reprocessing plants are described, conceptual designs are developed, and their effectiveness is evaluated. A technical approach to design of containment/surveillance systems is presented, and design considerations are discussed. This is the second in a series of reports. The first described the basis for the study of international safeguards for reprocessing plants. In this second report, only containment/surveillance is discussed. The third report will discuss the integration of concepts for containment/surveillance and material accountancy

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)

Optimizing the IAEA safeguards system

International Nuclear Information System (INIS)

Drobysz, Sonia; Sitt, Bernard

2011-09-01

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

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

International Nuclear Information System (INIS)

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

1982-04-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1982-04-01

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

Safeguards First Principles Initiative at the Nevada Test Site

International Nuclear Information System (INIS)

Johnson, Geneva

2007-01-01

The Material Control and Accountability (MC and A) program at the Nevada Test Site (NTS) was selected as a test bed for the Safeguards First Principles Initiative (SFPI). The implementation of the SFPI is evaluated using the system effectiveness model and the program is managed under an approved MC and A Plan. The effectiveness model consists of an evaluation of the critical elements necessary to detect, deter, and/or prevent the theft or diversion of Special Nuclear Material (SNM). The modeled results indicate that the MC and A program established under this variance is still effective, without creating unacceptable risk. Extensive performance testing is conducted through the duration of the pilot to ensure the protection system is effective and no material is at an unacceptable risk. The pilot was conducted from January 1, 2007, through May 30, 2007. This paper will discuss the following activities in association with SFPI: (1) Development of Timeline; (2) Crosswalk of DOE Order and SFPI; (3) Peer Review; (4) Deviation; (5) MC and A Plan and Procedure changes; (6) Changes implemented at NTS; (7) Training; and (8) Performance Test

The present status of safeguards in Turkey

International Nuclear Information System (INIS)

Yilmazer, A.; Yuecel, A.

2001-01-01

Republic of Turkey signed Non-Proliferation Treaty (NPT) in Vienna, Austria on January 28, 1969 and the Treaty was ratified by Turkish Parliament on March 29, 1979. International Atomic Energy Agency (IAEA) and Republic of Turkey signed the Safeguards Agreement on June 30, 1981. Turkey accepted the international safeguards administered by IAEA and at the same time its subsidiary arrangements and Facility attachments were enforced for all nuclear facilities as an Non-Nuclear-Weapon State party to NPT. Regulation on Nuclear Materials Accounting and Control, which was prepared in accordance with Agreement Between the Government of Turkey and IAEA for the application of Safeguard in Connection with the Treaty on NPT, has been put into force since it was published in Official Gazette on September 10, 1997. This study presents the essential futures of national system of accounting for and control of nuclear materials in Turkey

Proliferation resistance characteristics of advanced nuclear energy systems: a safeguard ability point of view

International Nuclear Information System (INIS)

Sevini, F.; Cojazzi, G.G.M.; Renda, G.

2008-01-01

Among the international community there is a renewed interest in nuclear power systems as a major source for energy production in the near to mid future. This is mainly due to concerns connected with future availability of conventional energy resources, and with the environmental impact of fossil fuels. International initiatives have been set up like the Generation 4. International Forum (GIF), the International Project on Innovative Nuclear Reactors and Fuel Cycles (IAEA-INPRO), and, partially, the US driven Global Nuclear Energy Partnership (GNEP), aimed at defining and evaluating the characteristics, in which future innovative nuclear energy systems (INS) will have to excel. Among the identified characteristics, Proliferation Resistance plays an important role for being able to widely deploy nuclear technology worldwide in a secure way. Studies having the objective to assess Proliferation Resistance of nuclear fuel cycles have been carried out since the nineteen seventies, e.g., the International Nuclear Fuel Cycle Evaluation (INFCE) and the Non-proliferation Alternative Systems Assessment Program (NASAP) initiatives, and all agree in stating that absolute intrinsic proliferation resistance, although desirable, is not achievable in the foreseeable future. The above finding is still valid; as a consequence, every INS will have to comply with agreements related to the Non Proliferation Treaty (NPT) and will require safeguards measures, implemented through extrinsic measures. This consideration led to a renewed interest in the Safeguard ability concept which can be seen as a bridge between intrinsic features and extrinsic features and measures.

International safeguards relevant to geologic disposal of high-level wastes and spent fuels

International Nuclear Information System (INIS)

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

1989-01-01

Spent fuels from once-through fuel cycles placed in underground repositories have the potential to become attractive targets for diversion and/or theft because of their valuable material content and decreasing radioactivity. The first geologic repository in the US, as currently designed, will contain approximately 500 Mt of plutonium, 60,000 Mt of uranium and a host of other fissile and strategically important elements. This paper identifies some of the international safeguards issues relevant to the various proposed scenarios for disposing of the spent fuel. In the context of the US program for geologic disposal of spent fuels, this paper highlights several issues that should be addressed in the near term by US industries, the Department of Energy, and the Nuclear Regulatory Commission before the geologic repositories for spent fuels become a reality. Based on US spent fuel discharges, an example is presented to illustrate the enormity of the problem of verifying spent fuel inventories. The geologic disposal scenario for high-level wastes originating from defense facilities produced a ''practicably irrecoverable'' waste form. Therefore, safeguards issues for geologic disposal of high-level waste now in the US are less pressing. 56 refs. , 2 figs

Noble gas atmospheric monitoring for international safeguards at reprocessing plants

International Nuclear Information System (INIS)

Nakhleh, C.W.; Poths, J.; Stanbro, W.D.; Perry, R.T. Jr.; Wilson, W.B.; Fearey, B.L.

1997-01-01

The use of environmental sampling is a major component of the improvements of International Atomic Energy Agency safeguards being carried out under Program 93+2. Nonradioactive noble gas isotopic measurements in the effluent stream of large reprocessing facilities may provide useful confirmatory information on the burnup and reactor type of the spent fuel undergoing reprocessing. The authors have taken and analyzed stack samples at an operating facility. The data show clear fission signals. The authors are currently applying a maximum-likelihood estimation procedure to determine the fuel burnup from these data. They anticipate that the general features involved in the table noble gas problem--selection of appropriate signals, measurement of those signals under realistic conditions, and inverse calculation of parameters of interest from the environmental data--will be present in all environmental sampling problems. These methods should therefore be widely applicable

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

Safeguards and security research and development: Progress report, October 1994--September 1995

Energy Technology Data Exchange (ETDEWEB)

Rutherford, D.R.; Henriksen, P.W. [comp.

1997-03-01

The primary goal of the Los Alamos Safeguards and Security Technology Development Program, International Safeguards, and other Safeguards and Security Programs is to continue to be the center of excellence in the field of Safeguards and Security. This annual report for 1995 describes those scientific and engineering projects that contribute to all of the aforementioned programs. The authors have presented the information in a different format from previous annual reports. Part I is devoted to Nuclear Material Measurement Systems. Part II contains projects that are specific to Integrated Safeguards Systems. Part III highlights Safeguards Systems Effectiveness Evaluations and Part IV is a compilation of highlights from Information Assurance projects. Finally Part V highlights work on the projects at Los Alamos for International Safeguards. The final part of this annual report lists titles and abstracts of Los Alamos Safeguards and Security Technology Development reports, technical journal articles, and conference papers that were presented and published in 1995. This is the last annual report in this format. The authors wish to thank all of the individuals who have contributed to this annual report and made it so successful over the years.

Safeguards and security research and development: Progress report, October 1994--September 1995

International Nuclear Information System (INIS)

Rutherford, D.R.; Henriksen, P.W.

1997-03-01

The primary goal of the Los Alamos Safeguards and Security Technology Development Program, International Safeguards, and other Safeguards and Security Programs is to continue to be the center of excellence in the field of Safeguards and Security. This annual report for 1995 describes those scientific and engineering projects that contribute to all of the aforementioned programs. The authors have presented the information in a different format from previous annual reports. Part I is devoted to Nuclear Material Measurement Systems. Part II contains projects that are specific to Integrated Safeguards Systems. Part III highlights Safeguards Systems Effectiveness Evaluations and Part IV is a compilation of highlights from Information Assurance projects. Finally Part V highlights work on the projects at Los Alamos for International Safeguards. The final part of this annual report lists titles and abstracts of Los Alamos Safeguards and Security Technology Development reports, technical journal articles, and conference papers that were presented and published in 1995. This is the last annual report in this format. The authors wish to thank all of the individuals who have contributed to this annual report and made it so successful over the years

Trade Analysis and Safeguards

International Nuclear Information System (INIS)

Chatelus, R.; Schot, P.M.

2010-01-01

In order to verify compliance with safeguards and draw conclusions on the absence of undeclared nuclear material and activities, the International Atomic Energy Agency (IAEA) collects and analyses trade information that it receives from open sources as well as from Member States. Although the IAEA does not intervene in national export controls, it has to monitor the trade of dual use items. Trade analysis helps the IAEA to evaluate global proliferation threats, to understand States' ability to report exports according to additional protocols but also to compare against State declarations. Consequently, the IAEA has explored sources of trade-related information and has developed analysis methodologies beyond its traditional safeguards approaches. (author)

The project 'nuclear safeguards'

International Nuclear Information System (INIS)

Gupta, D.

1976-01-01

A survey is given on the elaboration and implementation of a nuclear safeguards system which takes into account the economic needs of an expanding nuclear industry as well as the international monitoring commitments of the FRG under the Euratom and Non-Proliferation treaties. (RW) [de

Safeguarding of large scale reprocessing and MOX plants

International Nuclear Information System (INIS)

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

1997-01-01

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

Nuclear safeguards research and development. Program status report, October 1980-January 1981

International Nuclear Information System (INIS)

Henry, C.N.

1981-11-01

This report presents the status of the Nuclear Safeguards Research and Development Program pursued by the Energy, Chemistry-Materials Science, and Operational Security/Safeguards Divisions of the Los Alamos National Laboratory. Topics include nondestructive assay technology development and applications, international safeguards systems. Also discussed are training courses, technology transfer, analytical chemistry methods for fissionable materials safeguards, the Department of Energy Computer Security Technical Center, and operational security

Nuclear safeguards research and development. Program status report, October 1980-January 1981

Energy Technology Data Exchange (ETDEWEB)

Henry, C.N. (comp.)

1981-11-01

This report presents the status of the Nuclear Safeguards Research and Development Program pursued by the Energy, Chemistry-Materials Science, and Operational Security/Safeguards Divisions of the Los Alamos National Laboratory. Topics include nondestructive assay technology development and applications, international safeguards systems. Also discussed are training courses, technology transfer, analytical chemistry methods for fissionable materials safeguards, the Department of Energy Computer Security Technical Center, and operational security.

Non-proliferation and safeguards aspects of alternative fuel cycle concepts

International Nuclear Information System (INIS)

Persiani, P.J.

1997-01-01

Timely visibility on the development, evaluation and optimization of fuel cycle concepts with respect to nonproliferation characteristics should be emphasized in the early stage of planning a civilian nuclear power program, by fuel cycle developers, reviewers and decision makers. Fuel cycle technologies have inherently differing levels of nonproliferation characteristic profiles. Institutional and/or multi-national arrangements have been effective in reducing the nonproliferation concerns. The implementation of international safeguards further reduces these concerns by the timely detection of a possible physical diversion of SNM from fuel cycle facilities. Fuel cycles are safeguardable, but the nonproliferation characteristics of fuel cycle concepts differ significantly with consequent impacts on the international level of technical safeguards measures. The paper comments on characteristics of some of the fuel cycle concepts for the purpose of exploring the need to develop advanced nonproliferation and safeguards measures. (author)

Handbook of nuclear data for safeguards

International Nuclear Information System (INIS)

Lammer, M.; Schwerer, O.

1991-06-01

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

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.

The International Safeguards Technology Base: How is the Patient Doing? An Exploration of Effective Metrics

Energy Technology Data Exchange (ETDEWEB)

Schanfein, Mark J; Gouveia, Fernando S

2010-07-01

The term “Technology Base” is commonly used but what does it mean? Is there a common understanding of the components that comprise a technology base? Does a formal process exist to assess the health of a given technology base? These are important questions the relevance of which is even more pressing given the USDOE/NNSA initiatives to strengthen the safeguards technology base through investments in research & development and human capital development. Accordingly, the authors will establish a high-level framework to define and understand what comprises a technology base. Potential goal-driven metrics to assess the health of a technology base will also be explored, such as linear demographics and resource availability, in the hope that they can be used to better understand and improve the health of the U.S. safeguards technology base. Finally, through the identification of such metrics, the authors will offer suggestions and highlight choices for addressing potential shortfalls.

The International Safeguards Technology Base: How is the Patient Doing? An Exploration of Effective Metrics

International Nuclear Information System (INIS)

Schanfein, Mark J.; Gouveia, Fernando S.

2010-01-01

The term 'Technology Base' is commonly used but what does it mean? Is there a common understanding of the components that comprise a technology base? Does a formal process exist to assess the health of a given technology base? These are important questions the relevance of which is even more pressing given the USDOE/NNSA initiatives to strengthen the safeguards technology base through investments in research and development and human capital development. Accordingly, the authors will establish a high-level framework to define and understand what comprises a technology base. Potential goal-driven metrics to assess the health of a technology base will also be explored, such as linear demographics and resource availability, in the hope that they can be used to better understand and improve the health of the U.S. safeguards technology base. Finally, through the identification of such metrics, the authors will offer suggestions and highlight choices for addressing potential shortfalls.

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

Nuclear safeguards - a new profession

International Nuclear Information System (INIS)

Thorne, L.

1984-01-01

Early moves to restrict the proliferation of nuclear weapons are described together with the application of vigorous scientific techniques to the political framework of international treaties. Technical criteria for safeguards and verification methods are discussed. (U.K.)

IAEA Safeguards: Present status and experience gained

International Nuclear Information System (INIS)

Thorne, L.; Buechler, C.; Haegglund, E.

1983-01-01

IAEA safeguards are at the present under critical review with regard to their purpose and effectiveness. This paper describes the development of the IAEA Safeguards System from the early days, when procedures were developed on an ad hoc basis, to the present day. The development of State Systems of Accounting for and Control of Nuclear Material (SSAC), and of sophisticated instrumentation, has been necessary to deal with the rapid growth in the quantities of nuclear material and in the number of facilities under safeguards. The paper also discusses some of the managerial and organizational issues that are inherent in such a large international inspectorate. (author)

Enabling International Safeguards Research and Development in the United States

International Nuclear Information System (INIS)

Dwight, John E.; Schanfein, Mark J.; Bjornard, Trond A.

2009-01-01

Idaho National Laboratory (INL) is the lead laboratory in nuclear energy research and development within the U.S. Department of Energy national laboratory complex. INL is tasked with the advancement of nuclear energy research and development, and leadership in the renaissance of nuclear power globally. INL scientists have been central to the assessment of needs and the integration of technical programs aimed at the world-wide growth of nuclear power. One of the grand challenges of the nuclear energy resurgence is nuclear nonproliferation. Nonproliferation technology development is key to meeting this challenge. The needed advances in nonproliferation technologies are being made more difficult by the growing gap between increasing demands for nuclear materials to support technology development, and reduced availability of these materials. The gap is caused by the reduction, consolidation and more stringent lockdown of nuclear materials, made necessary by heightened and evolving security concerns, in the face of increased demand for materials to support technology development. Ironically, the increased demand for materials for technology development is made necessary by these same security concerns. The situation will continue to worsen if safeguards and security budgets remain limited for the International Atomic Energy Agency (IAEA) and many member states, while growth in global nuclear energy becomes a reality. Effective U.S. leadership in the closing of this gap is vital to homeland security and global stability. INL has taken positive steps, described in this paper, to close this gap by reestablishing a viable base for the development, testing and demonstration of safeguards and security technologies. Key attributes of this technology development base are (1) the availability of a wide variety of special nuclear materials in forms that allow for enhanced accessibility; (2) ease of access by U.S. government, national laboratory, industry and academic institution

Department of energy defense programs perspectives on safeguards, security, and classification

International Nuclear Information System (INIS)

Eyck, E.Q.T.

1989-01-01

This paper discusses why national and international safeguards and the protection of sensitive information are important to the United States and to other nations. It demonstrates that while the opposite consequence appears logical these functions will probably become even more important if the major powers agree on further arms reductions. Some of the steps taken by the U.S. Department of Energy to improve the effectiveness of its safeguards, security, and classification programs are reviewed. The valuable contributions in these areas since 1968 and 1976, respectively by the Technical Support Organization and the International Safeguards Project Offoce at Brookhaven are noted

Concept for fuel-cycle based safeguards

International Nuclear Information System (INIS)

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

1985-01-01

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

Agreement Between the Government of India and the International Atomic Energy Agency for the Application of Safeguards to Civilian Nuclear Facilities. Addition to the List of Facilities Subject to Safeguards Under the Agreement

International Nuclear Information System (INIS)

2014-01-01

In accordance with Paragraph 14(a) of the Agreement between the Government of India and the International Atomic Energy Agency for the Application of Safeguards to Civilian Nuclear Facilities (hereinafter “the Agreement”), India shall notify the Agency in writing of its decision to offer any facility identified by India for Agency safeguards under the Agreement. Any facility so notified by India becomes subject to the Agreement as of the date of receipt by the Agency of such written notification from India, and is to be included in the Annex to the Agreement. On 11 March 2014, the Agency received from India written notification, pursuant to Paragraph 14(a) of the Agreement, of its decision to bring one additional facility under safeguards in accordance with the provisions of the Agreement. Pursuant to Paragraph 14 4(a) of the Agreement, the Annex to the Agreement has been updated and is reproduced in this document for the information of all Members of the Agency

Agreement Between the Government of India and the International Atomic Energy Agency for the Application of Safeguards to Civilian Nuclear Facilities. Addition to the List of Facilities Subject to Safeguards Under the Agreement

International Nuclear Information System (INIS)

2014-01-01

In accordance with Paragraph 14(a) of the Agreement between the Government of India and the International Atomic Energy Agency for the Application of Safeguards to Civilian Nuclear Facilities (hereinafter “the Agreement”), India shall notify the Agency in writing of its decision to offer any facility identified by India for Agency safeguards under the Agreement. Any facility so notified by India becomes subject to the Agreement as of the date of receipt by the Agency of such written notification from India, and is to be included in the Annex to the Agreement. On 11 March 2014, the Agency received from India written notification, pursuant to Paragraph 14(a) of the Agreement, of its decision to bring one additional facility under safeguards in accordance with the provisions of the Agreement. Pursuant to Paragraph 14 4(a) of the Agreement, the Annex to the Agreement has been updated and is reproduced in this document for the information of all Members of the Agency [es

Safeguards and legal matters 1994. International Atomic Energy Agency Publications

International Nuclear Information System (INIS)

1995-01-01

This catalogue lists all sales publications of the International Atomic Energy Agency dealing with Safeguards and Legal Matters issued during the period 1970-1994. Most publications are published in English, through some are also available in French, Russian and Spanish. Proceedings of conferences, symposia and panels of experts may contain some papers in languages other than English (French, Russian or Spanish), but all of these papers have abstracts in English. If publications are also available in other languages than English, this is noted as C for Chinese, F for French, R for Russian and S for Spanish by the relevant ISBN number. It should be noted that prices of books are quoted in Austrian Schillings. The prices do not include local taxes and are subject to change without notice. All books in this catalogue are 16 x 24 cm, paper-bound, unless otherwise stated

Some problems relating to application of safeguards in the future

International Nuclear Information System (INIS)

Tolchenkov, D.L.

1983-01-01

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

Nuclear safeguards and security: we can do better.

Energy Technology Data Exchange (ETDEWEB)

Johnston, R. G. (Roger G.); Warner, Jon S.; Garcia, A. R. E. (Anthony R. E.); Martinez, R. K. (Ronald K.); Lopez, L. N. (Leon N.); Pacheco, A. N. (Adam N.); Trujillo, S. J. (Sonia J.); Herrera, A. M. (Alicia M.); Bitzer, E. G. (Edward G.), III

2005-01-01

There are a number of practical ways to significantly improve nuclear safeguards and security. These include recognizing and minimizing the insider threat; using adversarial vulnerability assessments to find vulnerabilities and countermeasures; fully appreciating the disparate nature of domestic and international nuclear safeguards; improving tamper detection and tamper-indicating seals; not confusing the inventory and security functions; and recognizing the limitations of GPS tracking, contact memory buttons, and RFID tags. The efficacy of nuclear safeguards depends critically on employing sophisticated security strategies and effective monitoring hardware. The Vulnerability Assessment Team (VAT) at Los Alamos National Laboratory has extensively researched issues associated with nuclear safeguards, especially in the areas of tamper/intrusion detection, transport security, and vulnerability assessments. This paper discusses some of our findings, recommendations, and warnings.

Safeguards as catastrophic risk management: insights and projections

International Nuclear Information System (INIS)

Leffer, T.N.

2013-01-01

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

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

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.

FY2017 Final Report: Power of the People: A technical ethical and experimental examination of the use of crowdsourcing to support international nuclear safeguards verification.

Energy Technology Data Exchange (ETDEWEB)

Gastelum, Zoe Nellie [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sentz, Kari [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Swanson, Meili Claire [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Rinaudo, Cristina [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-10-01

Recent advances in information technology have led to an expansion of crowdsourcing activities that utilize the “power of the people” harnessed via online games, communities of interest, and other platforms to collect, analyze, verify, and provide technological solutions for challenges from a multitude of domains. To related this surge in popularity, the research team developed a taxonomy of crowdsourcing activities as they relate to international nuclear safeguards, evaluated the potential legal and ethical issues surrounding the use of crowdsourcing to support safeguards, and proposed experimental designs to test the capabilities and prospect for the use of crowdsourcing to support nuclear safeguards verification.

Institutionalizing Safeguards By Design for Nuclear Facilities

International Nuclear Information System (INIS)

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

2008-01-01

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

Structure for the decomposition of safeguards responsibilities

International Nuclear Information System (INIS)

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

1977-01-01

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

Structure for the decomposition of safeguards responsibilities

International Nuclear Information System (INIS)

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

1977-08-01

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

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

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)

The legal regime of nuclear materials supply and international safeguards laid down in the EURATOM treaty, and how it has been modified by subsequent practice

International Nuclear Information System (INIS)

Manig, W.

1993-01-01