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Sample records for advanced safeguards approaches

  1. Advanced Safeguards Approaches for New Fast Reactors

    International Nuclear Information System (INIS)

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

    2007-01-01

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

  2. Advanced Safeguards Approaches for New Fast Reactors

    Energy Technology Data Exchange (ETDEWEB)

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

    2007-12-15

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

  3. 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)

  4. Advanced integrated safeguards at Barnwell

    International Nuclear Information System (INIS)

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

    1980-06-01

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

  5. IAEA safeguards approaches and goals

    International Nuclear Information System (INIS)

    Khlebnikov, Nikolai

    2001-01-01

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

  6. Recent advances in IAEA safeguards systems analysis

    International Nuclear Information System (INIS)

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

    1983-01-01

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

  7. 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

  8. 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

  9. Safeguards approach for irradiated fuel

    International Nuclear Information System (INIS)

    Harms, N.L.; Roberts, F.P.

    1987-03-01

    IAEA verification of irradiated fuel has become more complicated because of the introduction of variations in what was once presumed to be a straightforward flow of fuel from reactors to reprocessing plants, with subsequent dissolution. These variations include fuel element disassembly and reassembly, rod consolidation, double-tiering of fuel assemblies in reactor pools, long term wet and dry storage, and use of fuel element containers. This paper reviews future patterns for the transfer and storage of irradiated LWR fuel and discusses appropriate safeguards approaches for at-reactor storage, reprocessing plant headend, independent wet storage, and independent dry storage facilities

  10. Safeguards System for the Advanced Spent Fuel Conditioning Process Facility

    International Nuclear Information System (INIS)

    Kim, Ho-dong; Lee, T.H.; Yoon, J.S.; Park, S.W; Lee, S.Y.; Li, T.K.; Menlove, H.; Miller, M.C.; Tolba, A.; Zarucki, R.; Shawky, S.; Kamya, S.

    2007-01-01

    The advanced spent fuel conditioning process (ACP) which is a part of a pyro-processing has been under development at Korean Atomic Energy Research Institute (KAERI) since 1997 to tackle the problem of an accumulation of spent fuel. The concept is to convert spent oxide fuel into a metallic form in a high temperature molten salt in order to reduce the heat energy, volume, and radioactivity of a spent fuel. Since the inactive tests of the ACP have been successfully implemented to confirm the validity of the electrolytic reduction technology, a lab-scale hot test will be undertaken in a couple of years to validate the concept. For this purpose, the KAERI has built the ACP Facility (ACPF) at the basement of the Irradiated Material Examination Facility (IMEF) of KAERI, which already has a reserved hot-cell area. Through the bilateral arrangement between US Department of Energy (DOE) and Korean Ministry of Science and Technology (MOST) for safeguards R and D, the KAERI has developed elements of safeguards system for the ACPF in cooperation with the Los Alamos National Laboratory (LANL). The reference safeguards design conditions and equipment were established for the ACPF. The ACPF safeguards system has many unique design specifications because of the particular characteristics of the pyro-process materials and the restrictions during a facility operation. For the material accounting system, a set of remote operation and maintenance concepts has been introduced for a non-destructive assay (NDA) system. The IAEA has proposed a safeguards approach to the ACPF for the different operational phases. Safeguards measures at the ACPF will be implemented during all operational phases which include a 'Cold Test', a 'Hot Test' and at the end of a 'Hot test'. Optimization of the IAEA's inspection efforts was addressed by designing an effective safeguards approach that relies on, inter alia, remote monitoring using cameras, installed NDA instrumentation, gate monitors and seals

  11. Safeguardability of advanced spent fuel conditioning process

    Energy Technology Data Exchange (ETDEWEB)

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

    2004-01-01

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

  12. 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

  13. New approach to safeguards accounting

    International Nuclear Information System (INIS)

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

    1977-03-01

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

  14. 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)

  15. Combined SAFE/SNAP approach to safeguards evaluation

    International Nuclear Information System (INIS)

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

    1980-01-01

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

  16. 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

  17. Development of safeguards approach for the Rokkasho Reprocessing Plant

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  18. 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.

  19. 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)

  20. FY09 Advanced Instrumentation and Active Interrogation Research for Safeguards

    International Nuclear Information System (INIS)

    Chichester, D.L.; Pozzi, S.A.; Seabury, E.H.; Dolan, J.L.; Flaska, M.; Johnson, J.T.; Watson, S.M.; Wharton, J.

    2009-01-01

    Multiple small-scale projects have been undertaken to investigate advanced instrumentation solutions for safeguard measurement challenges associated with advanced fuel cycle facilities and next-generation fuel reprocessing installations. These activities are in support of the U.S. Department of Energy's Fuel Cycle Research and Development program and its Materials Protection, Accounting, and Control for Transmutation (MPACT) campaign. (1) Work was performed in a collaboration with the University of Michigan (Prof. Sara Pozzi, co-PI) to investigate the use of liquid-scintillator radiation detectors for assaying mixed-oxide (MOX) fuel, to characterize its composition and to develop advanced digital pulse-shape discrimination algorithms for performing time-correlation measurements in the MOX fuel environment. This work included both simulations and experiments and has shown that these techniques may provide a valuable approach for use within advanced safeguard measurement scenarios. (2) Work was conducted in a collaboration with Oak Ridge National Laboratory (Dr. Paul Hausladen, co-PI) to evaluate the strengths and weaknesses of the fast-neutron coded-aperture imaging technique for locating and characterizing fissile material, and as a tool for performing hold-up measurements in fissile material handling facilities. This work involved experiments at Idaho National Laboratory, using MOX fuel and uranium metal, in both passive and active interrogation configurations. A complete analysis has not yet been completed but preliminary results suggest several potential uses for the fast neutron imaging technique. (3) Work was carried out to identify measurement approaches for determining nitric acid concentration in the range of 1-4 M and beyond. This work included laboratory measurements to investigate the suitability of prompt-gamma neutron activation analysis for this measurement and product reviews of other commercial solutions. Ultrasonic density analysis appears to be

  1. 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

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

    International Nuclear Information System (INIS)

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

    1978-11-01

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

  3. 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)

  4. Combined SAFE/SNAP approach to safeguards evaluation

    International Nuclear Information System (INIS)

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

    1980-01-01

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

  5. Societal risk approach to safeguards design and evaluation

    International Nuclear Information System (INIS)

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

    1975-01-01

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

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

    International Nuclear Information System (INIS)

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

    2008-01-01

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

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

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  8. Advanced digital video surveillance for safeguard and physical protection

    International Nuclear Information System (INIS)

    Kumar, R.

    2002-01-01

    . These advanced surveillance systems aided with highly optimized video compression technologies over wireless and other communicating network media to provide security personnel real time, relevant only, timely information is going to be a great boon for physical security applications. This paper discusses some recent advances in digital video surveillance and its application in safeguard and physical protection. Refs. 5 (author)

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

    International Nuclear Information System (INIS)

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

    2010-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-01-01

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

  11. 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)

  12. 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

  13. ESARDA approach to facility oriented safeguards problems

    International Nuclear Information System (INIS)

    Stewart, R.

    1979-01-01

    The paper outlines the brief history of a Working Group composed of nuclear fuel plant operators, safeguards research workers and safeguards inspectors who are examining facility orientated problems of nuclear materials control and verification activities. The working program is reviewed together with some examples of various problems and the way the group is collaborating to develop solutions by pooling resources and effort. Work in European low enriched uranium fabrication plants from UF 6 to finished fuel is discussed in connection with mesurement practices, real time accounting, error propagation and analysis, verification and surveillance

  14. Safeguards approaches for conversion and gas centrifuge enrichment plants

    International Nuclear Information System (INIS)

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

    2013-01-01

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

  15. Needs of Advanced Safeguards Technologies for Future Nuclear Fuel Cycle (FNFC) Facilities and a Trial Application of SBD Concept to Facility Design of a Hypothetical FNFC Facility

    International Nuclear Information System (INIS)

    Seya, M.; Hajima, R.; Nishimori, N.; Hayakawa, T.; Kikuzawa, N.; Shizuma, T.; Fujiwara, M.

    2010-01-01

    Some of future nuclear fuel cycle (FNFC) facilities are supposed to have the characteristic features of very large throughput of plutonium, low decontamination reprocessing (no purification process; existence of certain amount of fission products (FP) in all process material), full minor actinides (MA) recycle, and treatment of MOX with FP and MA in fuel fabrication. In addition, the following international safeguards requirements have to be taken into account for safeguards approaches of the FNFC facilities. -Application of integrated safeguards (IS) approach; -Remote (unattended) verification; - 'Safeguards by Design' (SBD) concept. These features and requirements compel us to develop advanced technologies, which are not emerged yet. In order to realize the SBD, facility designers have to know important parts of design information on advanced safeguards systems before starting the facility design. The SBD concept requires not only early start of R and D of advanced safeguards technologies (before starting preliminary design of the facility) but also interaction steps between researchers working on safeguards systems and nuclear facility designers. The interaction steps are follows. Step-1; researchers show images of advanced safeguards systems to facility designers based on their research. Step-2; facility designers take important design information on safeguards systems into process systems of demonstration (or test) facility. Step-3; demonstration and improvement of both systems based on the conceptual design. Step-4; Construction of a FNFC facility with the advanced safeguards systems We present a trial application of the SBD concept to a hypothetical FNFC facility with an advanced hybrid K-edge densitometer and a Pu NDA system for spent nuclear fuel assembly using laser Compton scattering (LCS) X-rays and γ-rays and other advanced safeguards systems. (author)

  16. 2. JAPAN-IAEA workshop on advanced safeguards technology for the future nuclear fuel cycle. Abstracts

    International Nuclear Information System (INIS)

    2009-01-01

    This international workshop addressed issues and technologies associated with safeguarding the future nuclear fuel cycle. The workshop discussed issues of interest to the safeguards community, facility operators and State Systems of accounting and control of nuclear materials. Topic areas covered were as follows: Current Status and Future Prospects of Developing Safeguards Technologies for Nuclear Fuel Cycle Facilities, Technology and Instrumentation Needs, Advanced Safeguards Technologies, Guidelines on Developing Instrumentation to Lead the Way for Implementing Future Safeguards, and Experiences and Lessons learned. This workshop was of interest to individuals and organizations concerned with future nuclear fuel cycle technical developments and safeguards technologies. This includes representatives from the nuclear industry, R and D organizations, safeguards inspectorates, State systems of accountancy and control, and Member States Support Programmes

  17. Considerations on safeguards approach for small centrifuge enrichment facilities

    International Nuclear Information System (INIS)

    Vicens, Hugo E.; Marzo, Marco A.; Nunes, Vitorio E.

    2004-01-01

    The safeguards' objectives for enrichment facilities encompass the detection of the diversion of declared nuclear material and of facility misuse. The safeguard's approach presently applied for commercial centrifuge enrichment facilities is based on the Hexa partite Project and seems not to be directly applicable to cases of small plants. Since ABACC started its operation one of the main problems faced was the application of safeguards to small centrifuge enrichment plants for testing centrifuges in cascade mode or for small LEU production. These plants consist of a few fully independent cascades, does not operate in a routine basis and panels prevent visual access to the centrifuges and their surroundings for preserving sensitive information. For such plants misuse scenarios seems to dominate, particularly those associated with feeding the plant with undeclared LEU. This paper presents a concise analysis of misuse strategies in small centrifuge facility and alternative safeguard's approach, describing the main control elements to be applied. The particularities arising from the existence of panels or boxes covering the centrifuges are specifically addressed. Two alternatives approaches based on the application of a transitory perimeter control to increase the effectiveness of unannounced inspection and on the application of permanent perimeter control are presented. (author)

  18. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

    Robert Bean

    2010-09-01

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

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

    International Nuclear Information System (INIS)

    Suzuki, Mitsutoshi; Burr, Tom; Howell, John

    2011-01-01

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

  1. Task team approach to safeguards and security designs

    International Nuclear Information System (INIS)

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

    1991-01-01

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

  2. Safeguards in the European Union: The new partnership approach

    International Nuclear Information System (INIS)

    Thorstensen, S.; Chitumbo, K.

    1995-01-01

    This article highlights the circumstances surrounding the birth of the New Partnership Approach (NPA) and the status of its implementation. It particularly looks at elements of the NPA and practical arrangements that are being followed for specific types of nuclear and related facilities. Since elements of the NPA have been put into practice, significant savings have been realized in the allocation of safeguards inspection resources for Euratom countries, while ensuring effective verification. 1 graph, 1 tab

  3. An evaluation of safeguards approaches for neptunium

    International Nuclear Information System (INIS)

    Burr, Tom; Stanbro, William D.; Charlton, William

    2001-01-01

    The International Atomic Energy Agency has recently drawn attention to the fact that neptunium (Np), a byproduct of the nuclear power industry, can be used to make nuclear weapons. Current monitoring approaches for Np do not rely on material balance accounting as is used for uranium and plutonium. In the future this may change. Although full material balance accounting is not anticipated for Np, it is informative to evaluate the impact and benefit of full material balance accounting when considering other options. Therefore, this paper will apply systems analysis to evaluate ways to convert the current system to full materials balance accounting that will minimize the intrusiveness of the verification system and minimize costs to both the facility operator and the inspection agency. We then compare full material balance accounting to partial material balance accounting and to a ratio-monitoring technique referred to as flow sheet verification. We conclude that sampling approximately 25% of the batches is likely to be adequate and that Pu (or perhaps 137 Cs) will be the most effective surrogate for estimating the Np in the input accountability tank. (author)

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

    International Nuclear Information System (INIS)

    Sherr, T.S.

    1981-01-01

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

  5. Framework for fuel-cycle approaches to IAEA safeguards

    International Nuclear Information System (INIS)

    Fishbone, L.G.; Higinbotham, W.

    1986-01-01

    A framework is presented for comparing various safeguards verification approaches which have been proposed for consideration. Each inventory change, inventory, and material balance for each nuclear facility, reported by a state, may be verified. Verification approaches are compared by listing which of these reports would be verified and to what degree for each approach as they might be applied to a state with a closed fuel cycle. The comparison indicates that the extended-material-balance-area (or zone), the information-correlation, and the randomization-over-facilities approaches make more efficient use of Agency resources than the facility-oriented approach for states with large nuclear power programs. In contrast, any advantages of randomizing inspections over inspection activities within facilities are, percentagewise, relatively independent of the size of a state's nuclear program

  6. 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

  7. Automated approach to nuclear facility safeguards effectiveness evaluation

    International Nuclear Information System (INIS)

    1977-01-01

    Concern over the security of nuclear facilities has generated a need for a reliable, time efficient, and easily applied method of evaluating the effectiveness of safeguards systems. Such an evaluation technique could be used (1) by the Nuclear Regulatory Commission to evaluate a licensee's proposal, (2) to assess the security status of a system, or (3) to design and/or upgrade nuclear facilities. The technique should be capable of starting with basic information, such as the facility layout and performance parameters for physical protection components, and analyzing that information so that a reliable overall facility evaluation is obtained. Responding to this expressed need, an automated approach to facility safeguards effectiveness evaluation has been developed. This procedure consists of a collection of functional modules for facility characterization, critical path generation, and path evaluation combined into a continuous stream of operations. The technique has been implemented on an interactive computer-timesharing system and makes use of computer graphics for the handling and presentation of information. Using this technique a thorough facility evaluation can be made by systematically varying parameters that characterize the physical protection components of a facility according to changes in perceived adversary attributes and strategy, environmental conditions, and site status

  8. Advancements in Particle Analysis Procedures and their Application to the Characterization of Reference Materials for Safeguards

    International Nuclear Information System (INIS)

    Admon, U.; Chinea-Cano, E.; Dzigal, N.; Vogt, K.S.; Halevy, I.; Boblil, E.; Elkayam, T.; Weiss, A.

    2015-01-01

    Two approaches may be employed in the preparation of Reference Materials (RMs) for use in micro analytical techniques: placement of characterized micro artefacts in bulk materials and characterization of certain classes of individual particles in existing materials. In November 2013, a collaborative project was launched with the aim of adding information about such individual particles in existing RMs. The motivation behind this project was to investigate and characterize micro-artefacts present in certain commercially available RM, making them available and fit for use in safeguards and several other nuclear applications. The implementation and development of new techniques for particle characterization in bulk materials are also part of this project. The strategy for that approach includes the following steps: 1. Sample preparation: Dispersion of particles on stubs and planchets by an in-house shock-wave device. 2. Particle-of-Interest identification and characterization: (a) Fission Track (FT) route: Mosaic imaging of detectors containing FT stars; Applying automatic pattern recognition and localization of FT stars in detectors; Using Laser Micro-Dissection (LMD) for retrieval of individual particles; Preparation of sampled particles for SEM observation and other analytical techniques. (b) Alpha Track (αT) route: Direct particle identification and localization using position sensitive detectors (instrumental auto-radiography). (c) The advanced SEM route: Integration of analytical SEM techniques for characterization of individual particles of interest: EDS, mass spectrometry, FIB, micro-Raman. Preliminary results of the ongoing efforts will be reported. Utilization of these hyphenated techniques and instruments represents an innovative approach to particle characterization for Safeguards applications. (author)

  9. IAEA concerns about advanced containment and surveillance concepts or other alternative safeguards concepts

    International Nuclear Information System (INIS)

    von Baeckmann, A.; Powers, J.

    1981-01-01

    Nuclear material accountancy is used in IAEA safeguards as a measure of fundamental importance, with containment and surveillance as important complementary measures. Over the past five years the IAEA has worked with its Standing Advisory Group on Safeguards Implementation (SAGSI) to quantify major terms of the objectives, i.e., timeliness of detection, significant quantities and detection probabilities. The Agency is using those quantifications, as recommended by SAGSI, as guidelines for inspection planning and for evaluating the effectiveness of safeguards. The guidelines are used in this paper, together with other criteria like cost-effectiveness, compliance with legal limitation and non-intrusiveness, as yard-sticks for the assessment of the potential capabilities of alternative safeguards approaches. 4 refs

  10. The Site Approach - Lessons Learned from the Integrated Safeguards Approach for JNC-1

    International Nuclear Information System (INIS)

    Kikuchi, M.; Iso, S.; Tomine, K.; Hirato, Y.; Namekawa, M.; Takasugi, N.; Watanabe, M.; Tsutaki, Y.; Asano, T.; Nagatani, T.; Ninagawa, J.; Fujiwara, S.; Takahashi, S.; Kimura, T.; Kodani, Y.; Fukuhara, J.; Miyaji, N.; Kawakami, Y.; Koizumi, A.; Yamazaki, Y.; Nishinosono, S.; Sasaki, K.

    2010-01-01

    Integrated safeguards approaches for specific sites are recognized important elements in the design of a State-level approach under the concept of grouping facilities. Japan and the IAEA agreed further improvement of integrated safeguards implementation in effective and efficient manner, particularly at large complex nuclear sites in Japan. Japan and the IAEA developed the integrated safeguards approach for specific sites defined at Article 18 of Additional Protocol. In 2008, the IAEA started the three-year test implementation of JNC-1 site approach for improving the effectiveness and efficiency of the safeguards implementation of UDU material handling facilities. Japan and IAEA agreed to adopt the sector concept in order to make clear of subjected nuclear material to be verified. The sector is defined as spatial assignment that treats the same material stratum beyond MBAs in the site. The arrangement of MBAs and related material balance calculations as well as statistical analysis is maintained as a fundamental safeguards measure. At the boundaries of each sector, appropriate unattended NDA system and/or C/S system are installed, and material flows across the boundaries are verified by the system or attendance of resident inspectors. For inventory verification of the nuclear material stayed in sectors, an appropriate numbers of randomly scheduled inspections will be implemented. IAEA can access to the randomly selected sectors within 2 hours after notification. NRTA based on frequent operator's declaration will be performed for achievement of timeliness detection goal. The JNC-1 site approach has been implemented under the enhanced co-operation between the IAEA and SSAC through joint use of equipment and arrangements for DA analysis. Especially, national inspectors are working with IAEA together for coordination with operators. Because NMCC lab analyses all DA samples taken from facilities and the analysis results will be shared by the IAEA, certain numbers of DA

  11. Experience on implementation of the Integrated Safeguards approach for the MOX facility from the operator's point of view

    International Nuclear Information System (INIS)

    Nomi, Takayoshi; Nagatani, Taketeru; Ninagawa, Junichi; Nakajima, Shinji; Maruyama, Hajime; Asano, Takashi; Fujiwara, Shigeo

    2011-01-01

    The IS approach for the JNC-1 site was implemented in August 2008, and this was the first experience in the world. This IS approach aimed not only to improve efficiency and effectiveness of safeguards but also to reduce burden of the plant operation by improvement of efficiency of the inspection activity. It was planned to review effectiveness of this new approach after three years from implementation. And JAEA also evaluated effects by application of the IS approach for two MOX fuel facilities in the JNC-1 site based on the three years experiences from the operator's view point. As the result of evaluation, it was confirmed that there were some difference of benefits by application of the IS approach depending on features of the facility, automation level of equipment and advance level of safeguards systems. (author)

  12. Societal risk approach to safeguards design and evaluation

    International Nuclear Information System (INIS)

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

    1975-06-01

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

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

    International Nuclear Information System (INIS)

    Dreicer, J.S.

    1999-01-01

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

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

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  15. The status of the safeguards implementation under the State-Level Approach at the HANARO

    International Nuclear Information System (INIS)

    Kim, H. S.; Lee, B. D.; Kim, I. C.; Kim, H. J.; Jung, J. A.; Lee, S. H.

    2016-01-01

    The IAEA developed the SLA(State-Level Approach) for the States in order to maximize effectiveness of safeguards in an environment of constrained resources. The SLA has been implemented at KAERI-Daejeon site in the ROK since 2015. The ten nuclear facilities and one LOF(Location Outsides Facility) of the KAERI-Daejeon site are grouped into three categories under the SLA. The HANARO(High flux Advanced Neutron Application ReactOr) and PIEF(Post Irradiation Examination Facility) are involved in the category I “self-contained capability” facilities that have at least one significant quantity of suitable nuclear material and which could support undeclared plutonium production/separation activities without other supporting infrastructures. This paper described the status of the safeguards implementation at the HANARO involved in the category I under the SLA. The status of a model inventory management system for a research reactor developed in 2013 was also investigated. In this paper, the features and status of the safeguards implementation of the HANARO under the SLA were analyzed. Under the SLA, the monthly, quarterly and annual advanced facility operational information for the HANARO has been submitted to the IAEA in a timely manner. The IAEA inspection at HANARO has been successfully performed under the SLA. It is expected that the safeguards implementation work at HANARO under the SLA has the similar level with that under IS. Under the SLA, the data occurred from the surveillance cameras and other equipment installed at HANARO enables to transmit remotely to the IAEA. The IAEA is targeting 2017~2018 to upgrade them. In addition, the development status of a model inventory management system for a research reactor was investigated. It aims at controlling the material inventory for the nuclear material accounting work and the convenient facility operation. The major functions of it are to trace the transfer history of the nuclear materials and non-nuclear materials

  16. The status of the safeguards implementation under the State-Level Approach at the HANARO

    Energy Technology Data Exchange (ETDEWEB)

    Kim, H. S.; Lee, B. D.; Kim, I. C.; Kim, H. J.; Jung, J. A.; Lee, S. H. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    The IAEA developed the SLA(State-Level Approach) for the States in order to maximize effectiveness of safeguards in an environment of constrained resources. The SLA has been implemented at KAERI-Daejeon site in the ROK since 2015. The ten nuclear facilities and one LOF(Location Outsides Facility) of the KAERI-Daejeon site are grouped into three categories under the SLA. The HANARO(High flux Advanced Neutron Application ReactOr) and PIEF(Post Irradiation Examination Facility) are involved in the category I “self-contained capability” facilities that have at least one significant quantity of suitable nuclear material and which could support undeclared plutonium production/separation activities without other supporting infrastructures. This paper described the status of the safeguards implementation at the HANARO involved in the category I under the SLA. The status of a model inventory management system for a research reactor developed in 2013 was also investigated. In this paper, the features and status of the safeguards implementation of the HANARO under the SLA were analyzed. Under the SLA, the monthly, quarterly and annual advanced facility operational information for the HANARO has been submitted to the IAEA in a timely manner. The IAEA inspection at HANARO has been successfully performed under the SLA. It is expected that the safeguards implementation work at HANARO under the SLA has the similar level with that under IS. Under the SLA, the data occurred from the surveillance cameras and other equipment installed at HANARO enables to transmit remotely to the IAEA. The IAEA is targeting 2017~2018 to upgrade them. In addition, the development status of a model inventory management system for a research reactor was investigated. It aims at controlling the material inventory for the nuclear material accounting work and the convenient facility operation. The major functions of it are to trace the transfer history of the nuclear materials and non-nuclear materials

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

    International Nuclear Information System (INIS)

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

    2003-04-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2003-04-01

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

  19. Protecting me from my Directive: Ensuring Appropriate Safeguards for Advance Directives in Dementia.

    Science.gov (United States)

    Auckland, Cressida

    2018-02-01

    With one in six people over 80 now suffering from dementia, advance directives provide an important means of empowerment. Upholding directives in the context of dementia, however, raises extra challenges, given the potential for the directive to conflict with an assessment of what is in the person's current best interests. Given the profound harm that tying a person with dementia to their previous wishes can do, it is essential that we have sufficient safeguards in place to ensure that we only uphold such directives where we can be sure they are truly autonomous and are intended to apply to the situation at hand-safeguards which are at present, severely lacking. This article will consider various mechanisms by which safeguards can be built into the legal regime to ensure that the original decision is autonomous, including making it mandatory for the person to undergo a consultation with a healthcare professional, which would involve a contemporaneous capacity assessment. Clinicians must also be confident that the directive applies to the situation at hand. Introducing formalities, including a standardised (though not mandatory) proforma, may help to enhance specificity about when the directive is triggered, and to what treatments it relates, to enable clinicians to better assess the directive's applicability. A national registry for advance directives might also be beneficial. It will be argued that health care professionals will have to play a much greater role in the drafting and registering of advance directives, if we are to feel comfortable in upholding them.

  20. Implications for advanced safeguards derived from PR and PP case study results

    International Nuclear Information System (INIS)

    Boyer, Brian D.

    2009-01-01

    should have such features in it if it is seen to have intrinsic proliferation resistance. The technical difficulty in diverting material from the ESFR is at least as strongly impacted by the adversaries overall technical capabilities as it is by the effort required to overcome those barriers intrinsic to the nuclear fuel cycle. The intrinsic proliferation resistance of the ESFR will affect how extrinsic measures in the safeguards approach for the ESFR will provide overall proliferation resistance

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-06-15

    proliferation resistance. The technical difficulty in diverting material from the ESFR is at least as strongly impacted by the adversaries overall technical capabilities as it is by the effort required to overcome those barriers intrinsic to the nuclear fuel cycle. The intrinsic proliferation resistance of the ESFR will affect how extrinsic measures in the safeguards approach for the ESFR will provide overall proliferation resistance. (authors)

  2. Safeguardability assessment on pilot-scale advanced spent fuel conditioning facility

    International Nuclear Information System (INIS)

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

    2006-01-01

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

  3. Analysis on approach of safeguards implementation at research reactor handling item count and bulk material

    International Nuclear Information System (INIS)

    Kim, Hyun Jo; Lee, Sung Ho; Lee, Byung Doo; Jung, Juang

    2016-01-01

    KiJang research reactor (KJRR) will be constructed to produce the radioisotope such as Mo-99 etc., provide the neutron transmutation doping (NTD) service of silicon, and develop the core technologies of research reactor. In this paper, the features of the process and nuclear material flow are reviewed and the material balance area (MBA) and key measurement point (KMP) are established based on the nuclear material flow. Also, this paper reviews the approach on safeguards and nuclear material accountancy at the facility level for Safeguards-by-Design at research reactor handling item count and bulk material. In this paper, MBA and KMPs are established through the analysis on facility features and major process at KJRR handling item count and bulk material. Also, this paper reviews the IAEA safeguards implementation and nuclear material accountancy at KJRR. It is necessary to discuss the safeguards approach on the fresh FM target assemblies and remaining uranium in the intermediate level liquid wastes

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2018-01-15

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

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

    International Nuclear Information System (INIS)

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

    2002-01-01

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

  6. Analysis on approach of safeguards implementation at research reactor handling item count and bulk material

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyun Jo; Lee, Sung Ho; Lee, Byung Doo; Jung, Juang [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    KiJang research reactor (KJRR) will be constructed to produce the radioisotope such as Mo-99 etc., provide the neutron transmutation doping (NTD) service of silicon, and develop the core technologies of research reactor. In this paper, the features of the process and nuclear material flow are reviewed and the material balance area (MBA) and key measurement point (KMP) are established based on the nuclear material flow. Also, this paper reviews the approach on safeguards and nuclear material accountancy at the facility level for Safeguards-by-Design at research reactor handling item count and bulk material. In this paper, MBA and KMPs are established through the analysis on facility features and major process at KJRR handling item count and bulk material. Also, this paper reviews the IAEA safeguards implementation and nuclear material accountancy at KJRR. It is necessary to discuss the safeguards approach on the fresh FM target assemblies and remaining uranium in the intermediate level liquid wastes.

  7. Advanced safeguards research and development plan with an emphasis on its impact on nuclear power-plant design

    International Nuclear Information System (INIS)

    Tobin, S.J.; Demuth, S.F.; Miller, M.C.; Swinhoe, M.T.; Thomas, K.E.

    2007-01-01

    One tool for reducing the concern of nuclear proliferation is enhanced safeguards. Present safeguards have evolved over the past 40 years, and future safeguards will grow from this strong base to implement new technologies for improving our ability to quantify nuclear material. This paper will give an overview of the advanced technology research and development plan for safeguarding. One of the research facilities planned by the Department of Energy is the Advanced Fuel Cycle Facility (AFCF), to develop a novel nuclear fuel recycling program. Since the Advanced Fuel Cycle Facility will receive and reprocess spent fuel and will fabricate fast-reactor fuel, a wide breadth of safeguards technologies is involved. A fundamental concept in safeguards is material control and accounting (MCA). 4 topics concerning MCA and requiring further research have been identified: 1) measuring spent fuel, 2) measuring the plutonium content in the electro-refiner with pyro-processing, 3) measuring plutonium in the presence of other actinides, and 4) measuring neptunium and americium in the presence of other actinides. As for the long-term research and development plan for the AFCF, it will include improving MCA techniques as well as introducing new techniques that are not related to MCA, for example, enhanced containment and surveillance, or enhanced process monitoring. The top priority will stay quantifying the plutonium as accurately as possible and to reach this purpose 4 relevant technologies have been identified: 1) the microcalorimeter, 2) the passive neutron-albedo reactivity, 3) list-mode data acquisition, and 4) a liquid-scintillator multiplicity counter. Incorporating safeguards into the initial design of AFCF (safeguards by design) is a central concept. As the technology research and development plan for the Advanced Fuel Cycle Facility is examined, particular attention will be given to safeguards technologies that may affect the physical design of nuclear power plants

  8. 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

  9. 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.

  10. 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.

  11. 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.

  12. 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.

  13. 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)

  14. 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)

  15. New approach for safeguarding enriched uranium hexafluoride bulk transfers

    International Nuclear Information System (INIS)

    Doeher, L.W.; Pontius, P.E.; Whetstone, J.R.

    1978-01-01

    The unique concepts of American National Standard ANSI N15.18-1975 ''Mass Calibration Techniques for Nuclear Material Control'' are discussed in regard to the establishment and maintenance of control of mass measurement of Uranium Hexafluoride (UF 6 ) both within and between facilities. Emphasis is placed on the role of control of the measurements between facilities, and thus establish decision points for detection of measurement problems and making safeguards judgments. The unique concepts include the use of artifacts of UF 6 packaging cylinders, calibrated by a central authority, to introduce the mass unit into all of the industries' weighing processes. These are called Replicate Mass Standards (RMS). This feat is accomplished by comparing the RMS to each facility's In-House Standards (IHS), also artifacts, and thence the usage of these IHS to quantify the systematic and random errors of each UF 6 mass measurement process. A recent demonstration, which exchanged UF 6 cylinders between two facilities, who used ANSI N15.18-1975 concepts and procedures is discussed. The discussion includes methodology and treatment of data for use in detection of measurement and safeguards problems. The discussion incorporates the methodology for data treatment and judgments concerning (1) the common base, (2) measurement process off-sets, (3) measurement process precision, and (4) shipper-receiver bulk measurement differences. From the evidence gained in the demonstration, conclusions are reached as to the usefulness of the realistic criteria for detection of mass measurement problems upon acceptance of the concepts of ANSI N15.18-1975

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

    International Nuclear Information System (INIS)

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

    1979-10-01

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

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

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  18. Advanced intelligence and mechanism approach

    Institute of Scientific and Technical Information of China (English)

    ZHONG Yixin

    2007-01-01

    Advanced intelligence will feature the intelligence research in next 50 years.An understanding of the concept of advanced intelligence as well as its importance will be provided first,and detailed analysis on an approach,the mechanism approach.suitable to the advanced intelligence research will then be flolowed.And the mutual relationship among mechanism approach,traditional approaches existed in artificial intelligence research,and the cognitive informatics will be discussed.It is interesting to discover that mechanism approach is a good one to the Advanced Intelligence research and a tmified form of the existed approaches to artificial intelligence.

  19. Near Real-Time Nondestructive Active Inspection Technologies Utilizing Delayed γ-Rays and Neutrons for Advanced Safeguards

    International Nuclear Information System (INIS)

    Hunt, Alan; Tobin, S. J.

    2015-01-01

    In this two year project, the research team investigated how delayed γ-rays from short-lived fission fragments detected in the short interval between irradiating pulses can be exploited for advanced safeguards technologies. This program contained experimental and modeling efforts. The experimental effort measured the emitted spectra, time histories and correlations of the delayed γ-rays from aqueous solutions and solid targets containing fissionable isotopes. The modeling effort first developed and benchmarked a hybrid Monte Carlo simulation technique based on these experiments. The benchmarked simulations were then extended to other safeguards scenarios, allowing comparisons to other advanced safeguards technologies and to investigate combined techniques. Ultimately, the experiments demonstrated the possible utility of actively induced delayed γ-ray spectroscopy for fissionable material assay.

  20. Near Real-Time Nondestructive Active Inspection Technologies Utilizing Delayed γ-Rays and Neutrons for Advanced Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Hunt, Alan [Idaho State Univ., Pocatello, ID (United States). Idaho Accelerator Center, Dept. of Physics; Reedy, E. T.E. [Idaho State Univ., Pocatello, ID (United States). Dept. of Phyics, Idaho Accelerator Center; Mozin, V. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Tobin, S. J. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States). Nuclear Nonproliferation

    2015-02-12

    In this two year project, the research team investigated how delayed γ-rays from short-lived fission fragments detected in the short interval between irradiating pulses can be exploited for advanced safeguards technologies. This program contained experimental and modeling efforts. The experimental effort measured the emitted spectra, time histories and correlations of the delayed γ-rays from aqueous solutions and solid targets containing fissionable isotopes. The modeling effort first developed and benchmarked a hybrid Monte Carlo simulation technique based on these experiments. The benchmarked simulations were then extended to other safeguards scenarios, allowing comparisons to other advanced safeguards technologies and to investigate combined techniques. Ultimately, the experiments demonstrated the possible utility of actively induced delayed γ-ray spectroscopy for fissionable material assay.

  1. Safeguards '85

    International Nuclear Information System (INIS)

    Gruemm, H.

    1981-01-01

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

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

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  3. 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

  4. 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

  5. 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

  6. 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

  7. A safeguards approach for a closed geological repository for spent fuel

    International Nuclear Information System (INIS)

    Meer, K. van der; Carchon, R.

    1999-01-01

    After closure of a geological repository a diversion of fissile material can only take place by excavating spent fuel containers and bringing them to the surface. Therefore mining activities are required, either by reopening the original shaft, by creating a new shaft or by approaching the containers underground via a neighbouring mine The recovery time of the stored spent fuel plays an important role in the determination of the timeliness criterion and, therefore, the inspection frequency of the site. Obviously, this frequency can create a financial constraint due to the infinite character of the spent fuel storage in a geological repository. Anomalies for detection of a possible diversion are undeclared mining activities. The safeguards approach has to assure Continuity Of Knowledge (COK) of the fissile material. By consequence, a safeguards approach that is developed for a closed repository, is influenced by the safeguards approach applied to an open. repository and a conditioning facility. A closed repository is verified by DIV. To perform the DIV satellite monitoring could be performed for surface verification and e.g. seismic techniques could be used for verification that no undeclared mining activities underground take place. Visual inspections of the site by inspectors have to reveal concealment methods used by a potential diverter. These measures should guarantee that the disposed spent fuel remains untouched. (author)

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

    International Nuclear Information System (INIS)

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

    1988-01-01

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

  9. Analysis on safeguard approach of radioactive waste at KIJANG research reactor

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-12-15

    KIJANG Research Reactor (KJRR) will be constructed in Busan in order to provide the self-sufficiency of RI demand including Mo-99, to increase the neutron transmutation doping (NTD) capacity and to develop and validate technologies related to the research reactor. Considering the categorization of nuclear facility such as item counting and bulk facility, HANARO which is another research reactors in Korea is item counting facility because physical/chemical forms of nuclear material are not changes. During the dissolving process, radioactive wastes containing nuclear material are occurred at KJRR. In this paper, the features of the KJRR are described and safeguards approach on the radioactive wastes containing nuclear material occurred at KJRR are reviewed. This paper reviews the safeguards approach on radioactive wastes containing nuclear materials occurred during FM production at KJRR. Most uranium dissolved during FM production process are collected in U filter cakes and very tiny amount of uranium will be remained in the ILLW.

  10. Reassessment of safeguards parameters

    Energy Technology Data Exchange (ETDEWEB)

    Hakkila, E.A.; Richter, J.L.; Mullen, M.F.

    1994-07-01

    The International Atomic Energy Agency is reassessing the timeliness and goal quantity parameters that are used in defining safeguards approaches. This study reviews technology developments since the parameters were established in the 1970s and concludes that there is no reason to relax goal quantity or conversion time for reactor-grade plutonium relative to weapons-grade plutonium. For low-enriched uranium, especially in countries with advanced enrichment capability there may be an incentive to shorten the detection time.

  11. Using a dual safeguard web-based interactive teaching approach in an introductory physics class

    Directory of Open Access Journals (Sweden)

    Lie-Ming Li

    2015-03-01

    Full Text Available We modified the Just-in-Time Teaching approach and developed a dual safeguard web-based interactive (DGWI teaching system for an introductory physics course. The system consists of four instructional components that improve student learning by including warm-up assignments and online homework. Student and instructor activities involve activities both in the classroom and on a designated web site. An experimental study with control groups evaluated the effectiveness of the DGWI teaching method. The results indicate that the DGWI method is an effective way to improve students’ understanding of physics concepts, develop students’ problem-solving abilities through instructor-student interactions, and identify students’ misconceptions through a safeguard framework based on questions that satisfy teaching requirements and cover all of the course material. The empirical study and a follow-up survey found that the DGWI method increased student-teacher interaction and improved student learning outcomes.

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

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  13. A 3S Risk ?3SR? Assessment Approach for Nuclear Power: Safety Security and Safeguards.

    Energy Technology Data Exchange (ETDEWEB)

    Forrest, Robert; Reinhardt, Jason Christian; Wheeler, Timothy A.; Williams, Adam David

    2017-11-01

    Safety-focused risk analysis and assessment approaches struggle to adequately include malicious, deliberate acts against the nuclear power industry's fissile and waste material, infrastructure, and facilities. Further, existing methods do not adequately address non- proliferation issues. Treating safety, security, and safeguards concerns independently is inefficient because, at best, it may not take explicit advantage of measures that provide benefits against multiple risk domains, and, at worst, it may lead to implementations that increase overall risk due to incompatibilities. What is needed is an integrated safety, security and safeguards risk (or "3SR") framework for describing and assessing nuclear power risks that can enable direct trade-offs and interactions in order to inform risk management processes -- a potential paradigm shift in risk analysis and management. These proceedings of the Sandia ePRA Workshop (held August 22-23, 2017) are an attempt to begin the discussions and deliberations to extend and augment safety focused risk assessment approaches to include security concerns and begin moving towards a 3S Risk approach. Safeguards concerns were not included in this initial workshop and are left to future efforts. This workshop focused on four themes in order to begin building out a the safety and security portions of the 3S Risk toolkit: 1. Historical Approaches and Tools 2. Current Challenges 3. Modern Approaches 4. Paths Forward and Next Steps This report is organized along the four areas described above, and concludes with a summary of key points. 2 Contact: rforres@sandia.gov; +1 (925) 294-2728

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-03-15

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

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

    International Nuclear Information System (INIS)

    Fritzell, Anni

    2006-03-01

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

  16. 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

  17. The Nuclear Energy Advanced Modeling and Simulation Safeguards and Separations Reprocessing Plant Toolkit

    Energy Technology Data Exchange (ETDEWEB)

    McCaskey, Alex [ORNL; Billings, Jay Jay [ORNL; de Almeida, Valmor F [ORNL

    2011-08-01

    This report details the progress made in the development of the Reprocessing Plant Toolkit (RPTk) for the DOE Nuclear Energy Advanced Modeling and Simulation (NEAMS) program. RPTk is an ongoing development effort intended to provide users with an extensible, integrated, and scalable software framework for the modeling and simulation of spent nuclear fuel reprocessing plants by enabling the insertion and coupling of user-developed physicochemical modules of variable fidelity. The NEAMS Safeguards and Separations IPSC (SafeSeps) and the Enabling Computational Technologies (ECT) supporting program element have partnered to release an initial version of the RPTk with a focus on software usability and utility. RPTk implements a data flow architecture that is the source of the system's extensibility and scalability. Data flows through physicochemical modules sequentially, with each module importing data, evolving it, and exporting the updated data to the next downstream module. This is accomplished through various architectural abstractions designed to give RPTk true plug-and-play capabilities. A simple application of this architecture, as well as RPTk data flow and evolution, is demonstrated in Section 6 with an application consisting of two coupled physicochemical modules. The remaining sections describe this ongoing work in full, from system vision and design inception to full implementation. Section 3 describes the relevant software development processes used by the RPTk development team. These processes allow the team to manage system complexity and ensure stakeholder satisfaction. This section also details the work done on the RPTk ``black box'' and ``white box'' models, with a special focus on the separation of concerns between the RPTk user interface and application runtime. Section 4 and 5 discuss that application runtime component in more detail, and describe the dependencies, behavior, and rigorous testing of its constituent components.

  18. The next generation safeguards initiative

    International Nuclear Information System (INIS)

    Tobey, William

    2008-01-01

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

  19. 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

  20. 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

  1. Safeguards Implementation at KAERI

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-05-15

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

  2. The Concept of Goals-Driven Safeguards

    International Nuclear Information System (INIS)

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

    2009-01-01

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

  3. Measures of safeguard and rehabilitation for landscape protection planning: a qualitative approach based on diversity indicators.

    Science.gov (United States)

    La Rosa, Daniele; Privitera, Riccardo; Martinico, Francesco; La Greca, Paolo

    2013-09-01

    Maintaining existing levels of landscape diversity is becoming more and more important for planning considering the increasing pressures on agricultural ecosystems due to soil sealing, sprawl processes and intensive agriculture. Norms for land-use regulation and measures for landscape Safeguard and Rehabilitation have to take into consideration these threats in landscape planning. Evaluating the diversity of agricultural ecosystems is a fundamental step for proposing sound approaches to planning and managing both soil and landscape, as well as maintaining the related ecosystem services. The paper proposes a method aimed at the qualitative evaluation of spatial diversity of agricultural landscapes using a reduced set of ecological indicators based on land-use vector data. Indicators are calculated for defined landscape units characterized by landscape homogeneity. GIS geoprocessing and spatial analysis functions are employed. The study area is the Province of Enna in Sicily (Italy), which is characterized by cultivation mosaics in its southern region, cereal cultivation in the central region and prevailing natural environments in the northern region. Results from the indicator calculations are used to define measures to be included in a Landscape Protection Plan. Safeguard and Rehabilitation measures are introduced, which link indicator scores to planning protection aims. The results highlight the relevance of some agricultural mosaics in proximity to streams and seasonal fluvial environments, where some undamaged natural environments are still present. For these areas, specific landscape safeguard measures are proposed to preserve their diversity features together with their original agricultural functions. The work shows that even with a reduced number of indicators, a differentiated set of measures can be proposed for a Landscape Protection Plan. Copyright © 2013 Elsevier Ltd. All rights reserved.

  4. 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.

  5. Objectives and techniques of an advanced safeguards system for the CANDU reactor

    International Nuclear Information System (INIS)

    Smith, R.M.; Zarecki, C.W.; Head, D.A.

    1981-01-01

    In 1975, Canada began to actively assist the IAEA with manpower and research and development efforts to meet this requirement for CANDU reactors. This paper describes various aspects of the CANDU safeguards scheme, including the containment and surveillance equipment that has been developed. It includes consideration of the following: objectives of the safeguards system, role of equipment in meeting system objectives, cost and maintenance of equipment, capabilities and limitations of equipment, and effectiveness of the scheme and equipment in providing assurance of diversion detection. 11 refs

  6. Passive and Active Fast-Neutron Imaging in Support of Advanced Fuel Cycle Initiative Safeguards Campaign

    International Nuclear Information System (INIS)

    Blackston, Matthew A.; Hausladen, Paul

    2010-01-01

    Results from safeguards-related passive and active coded-aperture fast-neutron imaging measurements of plutonium and highly enriched uranium (HEU) material configurations performed at Idaho National Laboratory s Zero Power Physics Reactor facility are presented. The imaging measurements indicate that it is feasible to use fast neutron imaging in a variety of safeguards-related tasks, such as monitoring storage, evaluating holdup deposits in situ, or identifying individual leached hulls still containing fuel. The present work also presents the first demonstration of imaging of differential die away fast neutrons.

  7. Experience of Integrated Safeguards Approach for Large-scale Hot Cell Laboratory

    International Nuclear Information System (INIS)

    Miyaji, N.; Kawakami, Y.; Koizumi, A.; Otsuji, A.; Sasaki, K.

    2010-01-01

    The Japan Atomic Energy Agency (JAEA) has been operating a large-scale hot cell laboratory, the Fuels Monitoring Facility (FMF), located near the experimental fast reactor Joyo at the Oarai Research and Development Center (JNC-2 site). The FMF conducts post irradiation examinations (PIE) of fuel assemblies irradiated in Joyo. The assemblies are disassembled and non-destructive examinations, such as X-ray computed tomography tests, are carried out. Some of the fuel pins are cut into specimens and destructive examinations, such as ceramography and X-ray micro analyses, are performed. Following PIE, the tested material, in the form of a pin or segments, is shipped back to a Joyo spent fuel pond. In some cases, after reassembly of the examined irradiated fuel pins is completed, the fuel assemblies are shipped back to Joyo for further irradiation. For the IAEA to apply the integrated safeguards approach (ISA) to the FMF, a new verification system on material shipping and receiving process between Joyo and the FMF has been established by the IAEA under technical collaboration among the Japan Safeguard Office (JSGO) of MEXT, the Nuclear Material Control Center (NMCC) and the JAEA. The main concept of receipt/shipment verification under the ISA for JNC-2 site is as follows: under the IS, the FMF is treated as a Joyo-associated facility in terms of its safeguards system because it deals with the same spent fuels. Verification of the material shipping and receiving process between Joyo and the FMF can only be applied to the declared transport routes and transport casks. The verification of the nuclear material contained in the cask is performed with the method of gross defect at the time of short notice random interim inspections (RIIs) by measuring the surface neutron dose rate of the cask, filled with water to reduce radiation. The JAEA performed a series of preliminary tests with the IAEA, the JSGO and the NMCC, and confirmed from the standpoint of the operator that this

  8. Inventory of safeguards software

    International Nuclear Information System (INIS)

    Suzuki, Mitsutoshi; Horino, Koichi

    2009-03-01

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

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

    International Nuclear Information System (INIS)

    Cartan, F.O.

    1981-04-01

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

  10. Integration of the advanced transparency framework to advanced nuclear systems : enhancing Safety, Operations, Security and Safeguards (SOSS)

    International Nuclear Information System (INIS)

    Mendez, Carmen Margarita; Rochau, Gary Eugene; Cleary, Virginia D.

    2008-01-01

    The advent of the nuclear renaissance gives rise to a concern for the effective design of nuclear fuel cycle systems that are safe, secure, nonproliferating and cost-effective. We propose to integrate the monitoring of the four major factors of nuclear facilities by focusing on the interactions between Safeguards, Operations, Security, and Safety (SOSS). We proposed to develop a framework that monitors process information continuously and can demonstrate the ability to enhance safety, operations, security, and safeguards by measuring and reducing relevant SOSS risks, thus ensuring the safe and legitimate use of the nuclear fuel cycle facility. A real-time comparison between expected and observed operations provides the foundation for the calculation of SOSS risk. The automation of new nuclear facilities requiring minimal manual operation provides an opportunity to utilize the abundance of process information for monitoring SOSS risk. A framework that monitors process information continuously can lead to greater transparency of nuclear fuel cycle activities and can demonstrate the ability to enhance the safety, operations, security and safeguards associated with the functioning of the nuclear fuel cycle facility. Sandia National Laboratories (SNL) has developed a risk algorithm for safeguards and is in the process of demonstrating the ability to monitor operational signals in real-time though a cooperative research project with the Japan Atomic Energy Agency (JAEA). The risk algorithms for safety, operations and security are under development. The next stage of this work will be to integrate the four algorithms into a single framework

  11. Improvement of Safeguards Practices in Armenia Through Implementation of Advanced Software

    International Nuclear Information System (INIS)

    Melkumyan, A.; Amirjanyan, A.

    2015-01-01

    The Agreement between the Republic Armenia (RA) and the International Atomic Energy Agency (IAEA) for the Application of Safeguards in connection with Treaty on the Non- Proliferation of Nuclear Weapons was signed on 23.09.1993 and the Protocol Additional to the Safeguards Agreement was ratified on 28.06.2004. In 2007 the RA invited the IAEA ISSAS mission that made recommendations the majority of which have been implemented. The Law of the RA on Safe Utilization of Atomic Energy for Peaceful Purposes establishes the provisions related to the safeguards implementation on state and facility levels, as well as provisions related to preparation and conduct of SG inspections at nuclear facilities and LOFs, preparation and submission of accounting reports and other. The Armenian Nuclear Regulatory Authority is responsible for the safeguards implementation on the state level. The ANRA also maintains the general ledger for LOFs, prepares the accounting reports and submits them to the IAEA. To improve the SG practices and provide with the efficient and continuous control over the nuclear materials, the Nuclear and Radiation Safety Center (ANRA’s TSO) developed an electronic database NUCMAT to maintain an accurate inventory, record all changes and provide recoverable history of all activities related to the nuclear materials present in the RA. The NUCMAT provides with automated access to the information on NM and is aimed to assist in efficient implementation of accounting and control of NM, storing data, generating the accounting reports in the format that meets the IAEA requirements, as well tables and maps and quick access to the data. At present the NUCMAT is in trial use by the ANRA specifically in relation to implementation of the accounting and control of nuclear materials in the LOFs. (author)

  12. 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

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

    International Nuclear Information System (INIS)

    Johnson, C.E.

    1980-01-01

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

  14. 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

  15. An application of the controllable unit approach (CUA) to the analysis of safeguards measurement systems

    International Nuclear Information System (INIS)

    Seabaugh, P.W.; Rogers, D.R.; Woltermann, H.A.; Fushimi, F.C.; Ciramella, A.F.

    1979-01-01

    The controllable unit approach (CUA) is a material control and accountability methodology that takes into account the system logic and statistical characteristics of a plant process through the formulation of closure equations. The methodology is adaptable to plant processes of varying degrees of design and operational complexity. No alteration or modification of a process is required to apply the methodology. Cost/benefits of refinements in, or changes to, the proposed measurement system are obtained as incremental cost. To encourage improved safeguards accountability, the United States Nuclear Regulatory Commission (NRC) has been considering the use of performance-oriented regulations to supplement those currently used. The study, sponsored by NRC/Office of Standards Development, evaluated CUA methodology to meet performance-oriented regulations. For this study, the criterion is defined as the detection of a material loss of two kilograms of SNM with 97.5% confidence. Specifically investigated were the timeliness of detection, the ability to localize material loss, process coverage, cost/benefits, and compatibility with other safeguards techniques such as diversion path analysis and data filtering. The feasibility of performance-oriented regulations is demonstrated. To use the system of closure equations fully, a procedure was developed to integrate formally the effect of both short-term and long-term closure equations into an overall systems criterion of performance. Both single and multiple diversion strategies are examined in order to show how the CUA method can protect against either strategy. Quantitative results show that combined closure equations improve the detection sensitivity to material loss, and that multiple diversions provide only diminishing returns. (author)

  16. 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

  17. 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

  18. 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

  19. 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

  20. The international safeguards and domestic safeguards and security interface

    International Nuclear Information System (INIS)

    Whitworth, A.

    1996-01-01

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

  1. 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.

  2. An Approach to Safeguards by Design (SBD) for Fuel Cycle Facilities

    International Nuclear Information System (INIS)

    Sankaran Nair, P.; Gangotra, S.; Karanam, R.

    2015-01-01

    Implementation of safeguards in bulk handling facilities such as fuel fabrication facilities and reprocessing facilities are a challenging task. This is attributed to the nuclear material present in the facility in the form of powder, pellet, green pellet, solution and gaseous. Additionally material hold up, material unaccounted for (MUF) and the operations carried out round the clock add to the difficulties in implementing safeguards. In facilities already designed or commissioned or operational, implementation of safeguards measures are relatively difficult. The authors have studied a number of measures which can be adopted at the design stage itself. Safeguard By Design (SBD) measures can help in more effective implementation of safeguards, reduction of cost and reduction in radiological dose to the installation personnel. The SBD measures in the power reactors are comparatively easier to implement than in the fuel fabrication plants, since reactors are item counting facilities while the fuel fabrication plants are bulk handling type of facilities and involves much rigorous nuclear material accounting methodology. The safeguards measures include technical measures like dynamic nuclear material accounting, near real time monitoring, remote monitoring, use of automation, facility imagery, Radio Frequency Identification (RFID) tagging, reduction of MUF in bulk handling facilities etc. These measures have been studied in the context of bulk handling facilities and presented in this paper. Incorporation of these measures at the design stage (SBD) is expected to improve the efficiency of safeguardability in such bulk handling and item counting facilities and proliferation resistance of nuclear material handled in such facilities. (author)

  3. 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)

  4. 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.

  5. Safeguards resource management

    International Nuclear Information System (INIS)

    Strait, R.S.

    1986-01-01

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

  6. 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.

  7. 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.

  8. 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

  9. Safeguards on nuclear waste

    International Nuclear Information System (INIS)

    Crawford, D.W.

    1995-01-01

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

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

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  11. Key Nuclear Verification Priorities: Safeguards and Beyond

    International Nuclear Information System (INIS)

    Carlson, J.

    2010-01-01

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

  12. Key Nuclear Verification Priorities - Safeguards and Beyond

    International Nuclear Information System (INIS)

    Carlson, J.

    2010-01-01

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

  13. A study of a zone approach to IAEA [International Atomic Energy Agency] safeguards: The low-enriched-uranium zone of a light-water-reactor fuel cycle

    International Nuclear Information System (INIS)

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

    1986-06-01

    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 conclusions regarding the effectiveness of safeguards for the individual facilities within a state. In this study it was convenient to define three zones in a state with a closed light-water-reactor nuclear fuel cycle. Each zone contains those facilities or parts thereof which use or process nuclear materials of the same safeguards significance: low-enriched uranium, radioactive spent fuel, or recovered plutonium. The possibility that each zone might be treated as an extended material balance area for safeguards purposes is under investigation. The approach includes defining the relevant features of the facilities in the three zones and listing the safeguards activities which are now practiced. This study has focussed on the fresh-fuel zone, 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. There are a number of possible safeguards approaches which fall between the two extremes. The intention is to develop a rational approach which will make it possible to compare the technical effectiveness and the inspection effort for the facility-oriented approach, for the approach involving the zone as a material balance area, and for some reasonable intermediate safeguards approaches

  14. A study of a zone approach to IAEA (International Atomic Energy Agency) safeguards: The low-enriched-uranium zone of a light-water-reactor fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

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

    1986-06-01

    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 conclusions regarding the effectiveness of safeguards for the individual facilities within a state. In this study it was convenient to define three zones in a state with a closed light-water-reactor nuclear fuel cycle. Each zone contains those facilities or parts thereof which use or process nuclear materials of the same safeguards significance: low-enriched uranium, radioactive spent fuel, or recovered plutonium. The possibility that each zone might be treated as an extended material balance area for safeguards purposes is under investigation. The approach includes defining the relevant features of the facilities in the three zones and listing the safeguards activities which are now practiced. This study has focussed on the fresh-fuel zone, 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. There are a number of possible safeguards approaches which fall between the two extremes. The intention is to develop a rational approach which will make it possible to compare the technical effectiveness and the inspection effort for the facility-oriented approach, for the approach involving the zone as a material balance area, and for some reasonable intermediate safeguards approaches.

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

    Directory of Open Access Journals (Sweden)

    Pamela Jagger

    2014-09-01

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

  16. Safeguards resource management

    International Nuclear Information System (INIS)

    Strait, R.S.

    1986-01-01

    Protecting nuclear materials is a challenging problem for facility managers. To counter the broad spectrum of potential threats, facility managers rely on diverse safeguards measures, including elements of physical protection, material control and accountability, and human reliability programs. Deciding how to upgrade safeguards systems involves difficult tradeoffs between increased protection and the costs and operational impact of protection measures. Effective allocation of safeguards and security resources requires a prioritization of systems upgrades based on a relative measure of upgrade benefits to upgrade costs. Analytical tools are needed to help safeguards managers measure the relative benefits and cost and allocate their limited resources to achieve balanced, cost-effective protection against the full spectrum of threats. This paper presents a conceptual approach and quantitative model that have been developed by Lawrence Livermore National Laboratory to aid safeguards managers

  17. 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.

  18. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-07-01

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

  20. Approach to integrate current safeguards measures with additional protocol requirements at national level

    International Nuclear Information System (INIS)

    Ramirez, R.

    2001-01-01

    Peru adhered to the Additional Protocol in March 2000 which was also approved by the Congress in May 2001. After approval by law the obligations derived from this Additional Protocol will be in force after 180 days. After the signing of the Protocol an approach was designed to help better fulfill these requirements in an integrated way with the previous measures. As first stage, a review of the current state of safeguards was undertaken. Under the current agreement (an INFCIRC/153 type agreement) the reporting is less complicated and inexpensive to be carried out because these reports include only the declared nuclear material and the features of declared facilities where the nuclear material is used. No other related facility or material or activity needs to be declared. In Peru there are only two MBAs where low enriched uranium (LEU) is used and the record system includes general ledgers, inventory records and operational books. The results of national inspections and copies of reports and communications sent to the IAEA are also kept in this system. Under the agreement and subsidiary arrangements material balance reports (MBR), physical inventory listings (PIL) and inventory change reports (ICR) are prepared and submitted to the IAEA at scheduled periods. The MBR and PIL reports are sent after yearly regular inspections carried out by the IAEA. The ICR is sent just every time when an import or export of nuclear material is made. The time devoted to carry out all of these activities is not so extensive for both the State System for Accountability and Control (SSAC) and the users because of the limited nuclear activities in the country. Because of the characteristics and limited quantities of nuclear material the efforts for inspection and reporting activities are few. Another subject under review was the procedure for controlling the imports of nuclear material. Under the current agreement this subject was not a problem, as all of the radioactive and nuclear

  1. 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)

  2. A study of safeguards approach for the area of plutonium evaporator in a large scale reprocessing plant

    International Nuclear Information System (INIS)

    Sakai, Hirotada; Ikawa, Koji

    1994-01-01

    A preliminary study on a safeguards approach for the chemical processing area in a large scale reprocessing plant has been carried out. In this approach, plutonium inventory at the plutonium evaporator will not be taken, but containment and surveillance (C/S) measures will be applied to ensure the integrity of an area specifically defined to include the plutonium evaporator. The plutonium evaporator area consists of the evaporator itself and two accounting points, i.e., one before the plutonium evaporator and the other after the plutonium evaporator. For newly defined accounting points, two alternative measurement methods, i.e., accounting vessels with high accuracy and flow meters, were examined. Conditions to provide the integrity of the plutonium evaporator area were also examined as well as other technical aspects associated with this approach. The results showed that an appropriate combination of NRTA and C/S measures would be essential to realize a cost effective safeguards approach to be applied for a large scale reprocessing plant. (author)

  3. The use of safeguards data for process monitoring in the Advanced Test Line for Actinide Separations

    International Nuclear Information System (INIS)

    Barnes, J.W.; Yarbro, S.L.

    1987-01-01

    Los Alamos is constructing an integrated process monitoring/materials control and accounting (PM/MC and A) system in the Advanced Testing Line for Actinide Separations (ATLAS) at the Los Alamos Plutonium Facility. The ATLAS will test and demonstrate new methods for aqueous processing of plutonium. The ATLAS will also develop, test, and demonstrate the concepts for integrated process monitoring/materials control and accounting. We describe how this integrated PM/MC and A system will function and provide benefits to both process research and materials accounting personnel

  4. 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

  5. Network adaptable information systems for safeguard applications

    International Nuclear Information System (INIS)

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

    1996-01-01

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

  6. Safeguards as an evolutionary system

    International Nuclear Information System (INIS)

    Carlson, J.

    1998-01-01

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

  7. A new approach to nuclear fuel safeguard enhancement through radionuclide profiling

    Science.gov (United States)

    Peterson, Aaron Dawon

    The United States has led the effort to promote peaceful use of nuclear power amongst states actively utilizing it as well as those looking to deploy the technology in the near future. With the attraction being demonstrated by various countries towards nuclear power comes the concern that a nation may have military aspirations for the use of nuclear energy. The International Atomic Energy Agency (IAEA) has established nuclear safeguard protocols and procedures to mitigate nuclear proliferation. The work herein proposed a strategy to further enhance existing safeguard protocols by considering safeguard in nuclear fuel design. The strategy involved the use of radionuclides to profile nuclear fuels. Six radionuclides were selected as identifier materials. The decay and transmutation of these radionuclides were analyzed in reactor operation environment. MCNPX was used to simulate a reactor core. The perturbation in reactivity of the core due to the loading of the radionuclides was insignificant. The maximum positive and negative reactivity change induced was at day 1900 with a value of 0.00185 +/- 0.00256 and at day 2000 with -0.00441 +/- 0.00249, respectively. The mass of the radionuclides were practically unaffected by transmutation in the core; the change in radionuclide inventory was dominated by natural decay. The maximum material lost due to transmutation was 1.17% in Eu154. Extraneous signals from fission products identical to the radionuclide compromised the identifier signals. Eu154 saw a maximum intensity change at EOC and 30 days post-irradiation of 1260% and 4545%, respectively. Cs137 saw a minimum change of 12% and 89%, respectively. Mitigation of the extraneous signals is cardinal to the success of the proposed strategy. The predictability of natural decay provides a basis for the characterization of the signals from the radionuclide.

  8. Safeguards on nuclear materials

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  9. 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.

  10. Safeguards for geological repositories

    International Nuclear Information System (INIS)

    Fattah, A.

    2000-01-01

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

  11. 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

  12. A DOE multi-site approach to safeguards integration with facility operations

    International Nuclear Information System (INIS)

    Ostenak, C.A.

    1987-01-01

    The Accountability Technology Exchange (ATEX) Working Group was established in October 1986 by the US Department of Energy (DOE) to help identify nuclear materials accountability measurement needs within the DOE plutonium community and recommend potential improvements. ATEX Working Group membership represents nuclear materials production, safeguards, nondestructive assay (NDA), and analytical chemistry at a multitude of DOE plutonium sites. Currently, the ATEX Working Group has identified twenty NDA accountability measurement needs that fall into five major classes: NDA standards representing various nuclear materials and matrix compositions; NDA for impure nuclear materials compounds, residues, and wastes; NDA for product-grade nuclear materials; NDA for nuclear materials process holdup and in-process inventory; and NDA for nuclear materials item control and verification. Specific needs within these classes have been evaluated and ranked for individual sites and for the total DOE plutonium community

  13. Nuclear safeguards

    International Nuclear Information System (INIS)

    Estrampres, J.

    2010-01-01

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

  14. International safeguards

    International Nuclear Information System (INIS)

    Sanders, B.; Ha Vinh Phuong

    1976-01-01

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

  15. Fuel cycle based safeguards

    International Nuclear Information System (INIS)

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

    1985-07-01

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

  16. Application of the Controllable Unit Approach (CUA) to analyzing safeguards measurement systems

    International Nuclear Information System (INIS)

    Seabaugh, P.W.; Rogers, D.R.; Woltermann, H.A.; Fushimi, F.C.; Ciramella, A.F.

    1978-01-01

    CUA is a material control and accountability methodology that takes into account the system logic and statistical characteristics of a plant process through the formulation of closure equations. The study evaluated CUA methodology to meet performance oriented regulations. The criterion is defined as the detection of a material loss of two kilograms of SNM with 97.5% confidence. Specifically investigated were the timeliness of detection, the ability to localize material loss, process coverage, cost/benefits, and compatibility with other safeguards techniques such as diversion path analysis and data filtering. The feasibility of performance-oriented regulations is demonstrated. To fully use the system of closure equations, a procedure was developed to formally integrate the effect of both short-term and long-term closure equations into an overall systems criterion of performance. Both single and multiple diversion strategies are examined in order to show how the CUA method can protect against either strategy. Quantitative results show that combined closure equations improve the detection sensitivity to material loss, and that multiple diversions provide only diminishing returns

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

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  18. Safeguard sleuths

    International Nuclear Information System (INIS)

    Lowry, D.

    1989-01-01

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

  19. Reactor safeguards

    CERN Document Server

    Russell, Charles R

    1962-01-01

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

  20. 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)

  1. IAEA safeguards and detection of undeclared nuclear activities

    International Nuclear Information System (INIS)

    Harry, R.J.S.

    1996-03-01

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

  2. IAEA safeguards and detection of undeclared nuclear activities

    Energy Technology Data Exchange (ETDEWEB)

    Harry, R.J.S.

    1996-03-01

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

  3. Advanced computational approaches to biomedical engineering

    CERN Document Server

    Saha, Punam K; Basu, Subhadip

    2014-01-01

    There has been rapid growth in biomedical engineering in recent decades, given advancements in medical imaging and physiological modelling and sensing systems, coupled with immense growth in computational and network technology, analytic approaches, visualization and virtual-reality, man-machine interaction and automation. Biomedical engineering involves applying engineering principles to the medical and biological sciences and it comprises several topics including biomedicine, medical imaging, physiological modelling and sensing, instrumentation, real-time systems, automation and control, sig

  4. Safeguards through secure automated fabrication

    International Nuclear Information System (INIS)

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

    1982-01-01

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

  5. Safeguards agreements - Their legal and conceptual basis

    International Nuclear Information System (INIS)

    Sanders, B.; Rainer, R.H.

    1977-01-01

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

  6. Advances in Ecological Speciation: an integrative approach.

    Science.gov (United States)

    Faria, Rui; Renaut, Sebastien; Galindo, Juan; Pinho, Catarina; Melo-Ferreira, José; Melo, Martim; Jones, Felicity; Salzburger, Walter; Schluter, Dolph; Butlin, Roger

    2014-02-01

    The role of natural selection in promoting reproductive isolation has received substantial renewed interest within the last two decades. As a consequence, the study of ecological speciation has become an extremely productive research area in modern evolutionary biology. Recent innovations in sequencing technologies offer an unprecedented opportunity to study the mechanisms involved in ecological speciation. Genome scans provide significant insights but have some important limitations; efforts are needed to integrate them with other approaches to make full use of the sequencing data deluge. An international conference 'Advances in Ecological Speciation' organized by the University of Porto (Portugal) aimed to review current progress in ecological speciation. Using some of the examples presented at the conference, we highlight the benefits of integrating ecological and genomic data and discuss different mechanisms of parallel evolution. Finally, future avenues of research are suggested to advance our knowledge concerning the role of natural selection in the establishment of reproductive isolation during ecological speciation. © 2013 John Wiley & Sons Ltd.

  7. 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.

  8. Modular construction approach for advanced nuclear plants

    International Nuclear Information System (INIS)

    Johnson, F.T.; Orr, R.S.; Boudreaux, C.P.

    1988-01-01

    Modular construction has been designated as one of the major features of the AP600 program, a small innovative 600-MW (electric) advanced light water reactor (ALWR) that is currently being developed by Westinghouse and its subcontractors. This program is sponsored by the US Department of Energy (DOE) in conjunction with several other DOE and Electric Power Research Institute ALWR programs. Two major objectives of the AP600 program are as follows: (1) to provide a cost of power competitive with other power generation alternatives; and (2) to provide a short construction schedule that can be met with a high degree of certainty. The AP600 plant addresses these objectives by providing a simplified plant design and an optimized plant arrangement that result in a significant reduction in the number and size of systems and components, minimizes the overall building volumes, and consequently reduces the required bulk quantities. However, only by adopting a modular construction approach for the AP600 can the full cost and schedule benefits be realized from the advances made in the plant systems design and plant arrangement. Modularization is instrumental in achieving both of the above objectives, but most of all, a total modularization approach is considered absolutely essential to ensure that an aggressive construction schedule can be met with a high degree of certainty

  9. Some basic concepts of fast breeder reactor safeguards

    International Nuclear Information System (INIS)

    Tkharev, E.; Walford, F.J.

    1987-04-01

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

  10. Structured Assessment Approach: a procedure for the assessment of fuel cycle safeguard systems

    International Nuclear Information System (INIS)

    Parziale, A.A.; Patenaude, C.J.; Renard, P.A.; Sacks, I.J.

    1980-01-01

    Lawrence Livermore National Laboratory has developed and tested for the United States Nuclear Regulatory Commission a procedure for the evaluation of Material Control and Accounting (MC and A) Systems at Nuclear Fuel Facilities. This procedure, called the Structured Assessment Approach, SAA, subjects the MC and A system at a facility to a series of increasingly sophisticated adversaries and strategies. A fully integrated version of the computer codes which assist the analyst in this assessment was made available in October, 1979. The concepts of the SAA and the results of the assessment of a hypothetical but typical facility are presented

  11. J. Safeguards

    International Nuclear Information System (INIS)

    1976-01-01

    Like many drugs, poisons, and explosives in common use in our society today, nuclear materials are dangerous. This was recognised well before the advent of nuclear power, and precautions have been taken to isolate the substances from the environment. The expected expansion of nuclear power generation, and consequent proliferation of the materials, has caused opponents of the industry to voice pessimism over the ability of the authorities to contain these substances. The author discusses the dangers associated with the illicit use of nuclear materials, and the safeguards employed to minimise the risks arising from the commercial exploitation of nuclear power

  12. 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

  13. Advanced Approach of Multiagent Based Buoy Communication.

    Science.gov (United States)

    Gricius, Gediminas; Drungilas, Darius; Andziulis, Arunas; Dzemydiene, Dale; Voznak, Miroslav; Kurmis, Mindaugas; Jakovlev, Sergej

    2015-01-01

    Usually, a hydrometeorological information system is faced with great data flows, but the data levels are often excessive, depending on the observed region of the water. The paper presents advanced buoy communication technologies based on multiagent interaction and data exchange between several monitoring system nodes. The proposed management of buoy communication is based on a clustering algorithm, which enables the performance of the hydrometeorological information system to be enhanced. The experiment is based on the design and analysis of the inexpensive but reliable Baltic Sea autonomous monitoring network (buoys), which would be able to continuously monitor and collect temperature, waviness, and other required data. The proposed approach of multiagent based buoy communication enables all the data from the costal-based station to be monitored with limited transition speed by setting different tasks for the agent-based buoy system according to the clustering information.

  14. Advanced Approach of Multiagent Based Buoy Communication

    Directory of Open Access Journals (Sweden)

    Gediminas Gricius

    2015-01-01

    Full Text Available Usually, a hydrometeorological information system is faced with great data flows, but the data levels are often excessive, depending on the observed region of the water. The paper presents advanced buoy communication technologies based on multiagent interaction and data exchange between several monitoring system nodes. The proposed management of buoy communication is based on a clustering algorithm, which enables the performance of the hydrometeorological information system to be enhanced. The experiment is based on the design and analysis of the inexpensive but reliable Baltic Sea autonomous monitoring network (buoys, which would be able to continuously monitor and collect temperature, waviness, and other required data. The proposed approach of multiagent based buoy communication enables all the data from the costal-based station to be monitored with limited transition speed by setting different tasks for the agent-based buoy system according to the clustering information.

  15. 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

  16. 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

  17. Promoting global safeguards cooperation: Argentine-U.S. technical achievements

    International Nuclear Information System (INIS)

    Owens, L.; Smith, C.

    1996-01-01

    The bilateral ENREN (Argentina National Nuclear Regulatory Board)-DOE Safeguards Agreement was signed by Dr. Dan Beninson, ENREN, and Dr. Kenneth Baker, DOE, at the Peaceful Uses Conference in Bariloche in 1994. Two major activities identified for immediate cooperation were: nondestructive assay (NDA) techniques for Pilcaniyeu, and advanced containment and surveillance at Embalse. Both of these are discussed here. While the activities of the past year and a half are significant, many more opportunities remain for valuable cooperative partnering to discover more effective and efficient ways to apply safeguards. Several that have been identified by ENREN and DOE for 1996 are: (1) environmental monitoring as a safeguards technique; (2) Pilcaniyeu measurement studies and joint IAEA support program activities; (3) information management and analysis tools; (4) safeguards analytical laboratory support; (5) study of the safeguards approach for Embalse; (6) expansion of the remote monitoring system at Embalse; (7) use of ground-penetrating radar technology at Embalse; and (8) computerized material control and accounting tools for Pilcaniyeu

  18. Setting priorities for safeguards upgrades

    International Nuclear Information System (INIS)

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

    1987-01-01

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

  19. 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

  20. Aggregated systems model for nuclear safeguards decisions

    International Nuclear Information System (INIS)

    1979-03-01

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

  1. Containment and surveillance - A principal IAEA safeguards measure

    International Nuclear Information System (INIS)

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

    1997-01-01

    The growth of the safeguards inspectorate of the Agency, spanning more than 40 years, has produced a variety of interesting subjects (legal, technical, political, etc.) for recollection, discussion, and study. Although the Agency was established in 1957, the first practical inspections did not occur until the early 1960s. In the early inspections, thee was little C/S equipment available, and no optical surveillance was used. However, by the third decade of the IAEA, the 1980s, many technology advances were made, and the level of C/S equipment activities increased. By the late 1980s, some 200 Twin Minolta film camera systems were deployed by the Agency for safeguards use. At the present time, the Agency is evaluating and beginning to implement remote monitoring as part of the Strengthened Safeguards System. However, adoption of remote monitoring by international agencies cannot occur rapidly because of the many technical and policy issues associated with this activity. A glimpse into the future indicates that an important element of safeguards instrumentation will be the merging of C/S and NDA equipment into integrated systems. The use of modern interior area monitors in International Safeguards also offers a great potential for advancing C/S measures. The research in microsensors is in its infancy, and the opportunities for their reducing the cost, increasing the life time, and increasing the reliability of sensors for safeguards applications are manifold. A period may be approaching in which the terminology of C/S will no longer have its original meaning, as integrated systems combining NDA instruments and C/S instruments are already in use and are expected to be the norm in the near future

  2. Advanced and secure architectural EHR approaches.

    Science.gov (United States)

    Blobel, Bernd

    2006-01-01

    Electronic Health Records (EHRs) provided as a lifelong patient record advance towards core applications of distributed and co-operating health information systems and health networks. For meeting the challenge of scalable, flexible, portable, secure EHR systems, the underlying EHR architecture must be based on the component paradigm and model driven, separating platform-independent and platform-specific models. Allowing manageable models, real systems must be decomposed and simplified. The resulting modelling approach has to follow the ISO Reference Model - Open Distributing Processing (RM-ODP). The ISO RM-ODP describes any system component from different perspectives. Platform-independent perspectives contain the enterprise view (business process, policies, scenarios, use cases), the information view (classes and associations) and the computational view (composition and decomposition), whereas platform-specific perspectives concern the engineering view (physical distribution and realisation) and the technology view (implementation details from protocols up to education and training) on system components. Those views have to be established for components reflecting aspects of all domains involved in healthcare environments including administrative, legal, medical, technical, etc. Thus, security-related component models reflecting all view mentioned have to be established for enabling both application and communication security services as integral part of the system's architecture. Beside decomposition and simplification of system regarding the different viewpoint on their components, different levels of systems' granularity can be defined hiding internals or focusing on properties of basic components to form a more complex structure. The resulting models describe both structure and behaviour of component-based systems. The described approach has been deployed in different projects defining EHR systems and their underlying architectural principles. In that context

  3. 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.

  4. An Approach to Building Capacity for Nuclear Security and Safeguards in Thailand and the Southeast Asian Region

    International Nuclear Information System (INIS)

    Pengvanich, P.; Chanyotha, S.; Nilsuwankosit, S.

    2016-01-01

    Full text: A master’s degree programme in nuclear security and safeguards has been developed and offered at Chulalongkorn University for the first time in 2013 in order to develop necessary human resources in the fields of nuclear security and safeguards who can continue to work, conduct research, or serve as educators in these fields in Thailand and the Southeast Asian region. The first group of 20 students joined the programme in 2013 and recently graduated. The programme was one-of-its-kind, as there have not been many similar specialized programmes in nuclear security and safeguards in the past. In this paper, challenges and lessons learned throughout the programme are reported. Experience from the pilot programme will be used to improve the next round of the programme which is expected to start in 2017. With this program, more nuclear knowledge can be shared and maintained among the Association of South East Asian Nations (ASEAN) countries to ensure the peaceful utilization of nuclear technology in the region. (author

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-01-27

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

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

    International Nuclear Information System (INIS)

    Corynen, G.C.

    1979-01-01

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

  7. Safeguards Technology Strategic Planning Pentachart

    International Nuclear Information System (INIS)

    Carroll, C. J.

    2017-01-01

    Builds on earlier strategic planning workshops conducted for SGIT, SGTS, and SGCP. Many of recommendations from these workshops have been successfully implemented at the IAEA. Provide a context for evaluating new approaches for anticipated safeguards challenges of the future. Approach used by government and military to plan for an uncertain future. Uses consensus decision-making.

  8. Multilayer Approach for Advanced Hybrid Lithium Battery

    KAUST Repository

    Ming, Jun

    2016-06-06

    Conventional intercalated rechargeable batteries have shown their capacity limit, and the development of an alternative battery system with higher capacity is strongly needed for sustainable electrical vehicles and hand-held devices. Herein, we introduce a feasible and scalable multilayer approach to fabricate a promising hybrid lithium battery with superior capacity and multivoltage plateaus. A sulfur-rich electrode (90 wt % S) is covered by a dual layer of graphite/Li4Ti5O12, where the active materials S and Li4Ti5O12 can both take part in redox reactions and thus deliver a high capacity of 572 mAh gcathode -1 (vs the total mass of electrode) or 1866 mAh gs -1 (vs the mass of sulfur) at 0.1C (with the definition of 1C = 1675 mA gs -1). The battery shows unique voltage platforms at 2.35 and 2.1 V, contributed from S, and 1.55 V from Li4Ti5O12. A high rate capability of 566 mAh gcathode -1 at 0.25C and 376 mAh gcathode -1 at 1C with durable cycle ability over 100 cycles can be achieved. Operando Raman and electron microscope analysis confirm that the graphite/Li4Ti5O12 layer slows the dissolution/migration of polysulfides, thereby giving rise to a higher sulfur utilization and a slower capacity decay. This advanced hybrid battery with a multilayer concept for marrying different voltage plateaus from various electrode materials opens a way of providing tunable capacity and multiple voltage platforms for energy device applications. © 2016 American Chemical Society.

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

    International Nuclear Information System (INIS)

    1978-11-01

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

  10. The Advanced German Course: A Multidimensional Approach.

    Science.gov (United States)

    Lutcavage, Charles

    1990-01-01

    Describes an advanced language course that focuses on modern German culture and society, and emphasizes advanced reading, grammar, conversation, and composition. This framework can be enhanced by regular incorporation of audio and video technology into the program as a means of heightening students' awareness of language and topical issues.…

  11. 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

  12. Safeguards implications of laser isotope separation

    International Nuclear Information System (INIS)

    Moriarty, T.F.; Taylor, K.

    1993-10-01

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

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

    International Nuclear Information System (INIS)

    JOE, J.

    2007-01-01

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

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

    International Nuclear Information System (INIS)

    Metcalf, Richard; Bean, Robert

    2009-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Richard Metcalf; Robert Bean

    2009-10-01

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

  16. A Safeguardability Check-List for Safeguards by Design

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-12-15

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

  17. Next Generation Safeguards Initiative: 2010 and Beyond

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  18. 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.

  19. 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

  20. International safeguards 1979

    International Nuclear Information System (INIS)

    Fischer, D.

    1979-01-01

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

  1. 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

  2. Technology Development of Safeguards

    Energy Technology Data Exchange (ETDEWEB)

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

    2007-04-15

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

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

    International Nuclear Information System (INIS)

    Beddingfield, David H.; Lafleur, Adrienne M.

    2009-01-01

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

  4. 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.

  5. 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.

  6. Nuclear safeguards technology handbook

    Energy Technology Data Exchange (ETDEWEB)

    1977-12-01

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

  7. Nuclear safeguards technology handbook

    International Nuclear Information System (INIS)

    1977-12-01

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

  8. Linear induction accelerator approach for advanced radiography

    International Nuclear Information System (INIS)

    Caporaso, G.J.

    1997-05-01

    Recent advances in induction accelerator technology make it possible to envision a single accelerator that can serve as an intense, precision multiple pulse x-ray source for advanced radiography. Through the use of solid-state modulator technology repetition rates on the order of 1 MHz can be achieved with beam pulse lengths ranging from 200 ns to 2 microsecs. By using fast kickers, these pulses may be sectioned into pieces which are directed to different beam lines so as to interrogate the object under study from multiple lines of sight. The ultimate aim is to do a time dependent tomographic reconstruction of a dynamic object. The technology to accomplish these objectives along with a brief discussion of the experimental plans to verify it will be presented

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

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  10. Use of curium neutron flux from head-end pyroprocessing subsystems for the High Reliability Safeguards methodology

    Energy Technology Data Exchange (ETDEWEB)

    Borrelli, R.A., E-mail: r.angelo.borrelli@gmail.com

    2014-10-01

    The deployment of nuclear energy systems (NESs) is expanding around the world. Nations are investing in NESs as a means to establish energy independence, grow national economies, and address climate change. Transitioning to the advanced nuclear fuel cycle can meet growing energy demands and ensure resource sustainability. However, nuclear facilities in all phases of the advanced fuel cycle must be ‘safeguardable,’ where safety, safeguards, and security are integrated into a practical design strategy. To this end, the High Reliability Safeguards (HRS) approach is a continually developing safeguardability methodology that applies intrinsic design features and employs a risk-informed approach for systems assessment that is safeguards-motivated. Currently, a commercial pyroprocessing facility is used as the example system. This paper presents a modeling study that investigates the neutron flux associated with processed materials. The intent of these studies is to determine if the neutron flux will affect facility design, and subsequently, safeguardability. The results presented in this paper are for the head-end subsystems in a pyroprocessing facility. The collective results from these studies will then be used to further develop the HRS methodology.

  11. Implementing Safeguards-by-Design

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  12. Safeguards in the Slovak Republic

    International Nuclear Information System (INIS)

    Vaclav, J.

    2010-01-01

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

  13. Measurement trends for future safeguards systems

    International Nuclear Information System (INIS)

    Baloga, S.M.; Hakkila, E.A.

    1980-01-01

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

  14. Advances in particle therapy a multidisciplinary approach

    CERN Document Server

    Bernier, Jacques

    2018-01-01

    Hadron therapy is a groundbreaking new method of treating cancer. Boasting greater precision than other therapies, this therapy is now utilised in many clinical settings and the field is growing. More than 50 medical facilities currently perform (or are planned to perform) this treatment, with this number set to double by 2020. This new text covers the most recent advances in hadron therapy, exploring the physics, technology, biology, diagnosis, clinical applications, and economics behind the therapy. Providing essential and up-to-date information on recent developments in the field, this book will be of interest to current and aspiring specialists from a wide range of backgrounds.

  15. Safeguards instrumentation: past, present, future

    International Nuclear Information System (INIS)

    Higinbotham, W.A.

    1982-01-01

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

  16. Safeguards agreements - their legal and conceptual basis

    International Nuclear Information System (INIS)

    Sanders, B.; Rainer, R.

    1977-01-01

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

  17. Safeguards Automated Facility Evaluation (SAFE) methodology

    International Nuclear Information System (INIS)

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

    1978-08-01

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

  18. Safeguards and retrievability from waste forms

    Energy Technology Data Exchange (ETDEWEB)

    Danker, W.

    1996-05-01

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

  19. Optimizing the IAEA safeguards system

    International Nuclear Information System (INIS)

    Drobysz, Sonia; Sitt, Bernard

    2011-09-01

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

  20. 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

  1. 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

  2. Advancing a holistic approach to openness

    DEFF Research Database (Denmark)

    Søndergaard, Helle Alsted; Araújo, Ana Luiza Lara de

    Open innovation has emerged as a new and interesting research area, and with this paper we wish to contribute to the research on open innovation by proposing a more holistic approach to openness that includes the internal sphere of openness. We use data from 170 Danish SMEs in the high-tech and m......Open innovation has emerged as a new and interesting research area, and with this paper we wish to contribute to the research on open innovation by proposing a more holistic approach to openness that includes the internal sphere of openness. We use data from 170 Danish SMEs in the high...

  3. PROBLEMS AND PROSPECTS OF SAFEGUARDING HEALTH ...

    African Journals Online (AJOL)

    observes that problems of safeguarding health values and right to health in ... through organized strategies and new approaches deliberately instituted to ... conceptions of a group about what is bad, undesirable and improper towards their ...

  4. Achieving the Benefits of Safeguards by Design

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  5. Approaches for advancing scientific understanding of macrosystems

    Science.gov (United States)

    Levy, Ofir; Ball, Becky A.; Bond-Lamberty, Ben; Cheruvelil, Kendra S.; Finley, Andrew O.; Lottig, Noah R.; Surangi W. Punyasena,; Xiao, Jingfeng; Zhou, Jizhong; Buckley, Lauren B.; Filstrup, Christopher T.; Keitt, Tim H.; Kellner, James R.; Knapp, Alan K.; Richardson, Andrew D.; Tcheng, David; Toomey, Michael; Vargas, Rodrigo; Voordeckers, James W.; Wagner, Tyler; Williams, John W.

    2014-01-01

    The emergence of macrosystems ecology (MSE), which focuses on regional- to continental-scale ecological patterns and processes, builds upon a history of long-term and broad-scale studies in ecology. Scientists face the difficulty of integrating the many elements that make up macrosystems, which consist of hierarchical processes at interacting spatial and temporal scales. Researchers must also identify the most relevant scales and variables to be considered, the required data resources, and the appropriate study design to provide the proper inferences. The large volumes of multi-thematic data often associated with macrosystem studies typically require validation, standardization, and assimilation. Finally, analytical approaches need to describe how cross-scale and hierarchical dynamics and interactions relate to macroscale phenomena. Here, we elaborate on some key methodological challenges of MSE research and discuss existing and novel approaches to meet them.

  6. Delivering advanced therapies: the big pharma approach.

    Science.gov (United States)

    Tarnowski, J; Krishna, D; Jespers, L; Ketkar, A; Haddock, R; Imrie, J; Kili, S

    2017-09-01

    After two decades of focused development and some recent clinical successes, cell and gene therapy (CGT) is emerging as a promising approach to personalized medicines. Genetically engineered cells as a medical modality are poised to stand alongside or in combination with small molecule and biopharmaceutical approaches to bring new therapies to patients globally. Big pharma can have a vital role in industrializing CGT by focusing on diseases with high unmet medical need and compelling genetic evidence. Pharma should invest in manufacturing and supply chain solutions that deliver reproducible, high-quality therapies at a commercially viable cost. Owing to the fast pace of innovation in this field proactive engagement with regulators is critical. It is also vital to understand the needs of patients all along the patient care pathway and to establish product pricing that is accepted by prescribers, payers and patients.

  7. Advanced drug delivery approaches against periodontitis.

    Science.gov (United States)

    Joshi, Deeksha; Garg, Tarun; Goyal, Amit K; Rath, Goutam

    2016-01-01

    Periodontitis is an inflammatory disease of gums involving the degeneration of periodontal ligaments, creation of periodontal pocket and resorption of alveolar bone, resulting in the disruption of the support structure of teeth. According to WHO, 10-15% of the global population suffers from severe periodontitis. The disease results from the growth of a diverse microflora (especially anaerobes) in the pockets and release of toxins, enzymes and stimulation of body's immune response. Various local or systemic approaches were used for an effective treatment of periodontitis. Currently, controlled local drug delivery approach is more favorable as compared to systemic approach because it mainly focuses on improving the therapeutic outcomes by achieving factors like site-specific delivery, low dose requirement, bypass of first-pass metabolism, reduction in gastrointestinal side effects and decrease in dosing frequency. Overall it provides a safe and effective mode of treatment, which enhances patient compliance. Complete eradication of the organisms from the sites was not achieved by using various surgical and mechanical treatments. So a number of polymer-based delivery systems like fibers, films, chips, strips, microparticles, nanoparticles and nanofibers made from a variety of natural and synthetic materials have been successfully tested to deliver a variety of drugs. These systems are biocompatible and biodegradable, completely fill the pockets, and have strong retention on the target site due to excellent mucoadhesion properties. The review summarizes various available and recently developing targeted delivery devices for the treatment of periodontitis.

  8. Nuclear Safeguards Culture

    International Nuclear Information System (INIS)

    Findlay, T.

    2015-01-01

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

  9. 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.

  10. 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)

  11. Long-Term Information Management (LTIM) of Safeguards Data at Repositories: Phase II

    International Nuclear Information System (INIS)

    Haddal, Risa N.

    2016-01-01

    One of the challenges of implementing safeguards for geological repositories will be the long-term preservation of safeguards-related data for 100 years or more. While most countries considering the construction and operation of such facilities agree that safeguards information should be preserved, there are gaps with respect to standardized requirements, guidelines, timescales, and approaches. This study analyzes those gaps and explores research to clarify stakeholder needs, identify current policies, approaches, best practices and international standards, and explores existing safeguards information management infrastructure. The study also attempts to clarify what a safeguards data classification system might look like, how long data should be retained, and how information should be exchanged between stakeholders at different phases of a repository's life cycle. The analysis produced a variety of recommendations on what information to preserve, how to preserve it, where to store it, retention options and how to exchange information in the long term. Key findings include the use of the globally recognized international records management standard, ISO15489, for guidance on the development of information management systems, and the development of a Key Information File (KIF). The KIF could be used to identify only the most relevant, high-level safeguards information and the history of decision making about the repository. The study also suggests implementing on-site and off-site records storage in digital and physical form; developing a safeguards data classification system; long-term records retention with periodic reviews every 5 to 10 years during each phase of the repository life cycle; and establishing transition procedures well in advance so that data shepherds and records officers can transfer information with incoming facility managers effectively and efficiently. These and other recommendations are further analyzed in this study.

  12. Long-Term Information Management (LTIM) of Safeguards Data at Repositories: Phase II

    Energy Technology Data Exchange (ETDEWEB)

    Haddal, Risa N. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-10-01

    One of the challenges of implementing safeguards for geological repositories will be the long-term preservation of safeguards-related data for 100 years or more. While most countries considering the construction and operation of such facilities agree that safeguards information should be preserved, there are gaps with respect to standardized requirements, guidelines, timescales, and approaches. This study analyzes those gaps and explores research to clarify stakeholder needs, identify current policies, approaches, best practices and international standards, and explores existing safeguards information management infrastructure. The study also attempts to clarify what a safeguards data classification system might look like, how long data should be retained, and how information should be exchanged between stakeholders at different phases of a repository’s life cycle. The analysis produced a variety of recommendations on what information to preserve, how to preserve it, where to store it, retention options and how to exchange information in the long term. Key findings include the use of the globally recognized international records management standard, ISO15489, for guidance on the development of information management systems, and the development of a Key Information File (KIF). The KIF could be used to identify only the most relevant, high-level safeguards information and the history of decision making about the repository. The study also suggests implementing on-site and off-site records storage in digital and physical form; developing a safeguards data classification system; long-term records retention with periodic reviews every 5 to 10 years during each phase of the repository life cycle; and establishing transition procedures well in advance so that data shepherds and records officers can transfer information with incoming facility managers effectively and efficiently. These and other recommendations are further analyzed in this study.

  13. Structure of safeguards systems

    International Nuclear Information System (INIS)

    Shipley, J.P.

    1978-06-01

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

  14. 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

  15. Nuclear safeguards policy

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

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

  16. Transit Matching for International Safeguards

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  17. 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

  18. Advanced control room evaluation: General approach and rationale

    International Nuclear Information System (INIS)

    O'Hara, J.M.; Wachtel, J.

    1991-01-01

    Advanced control rooms (ACRs) for future nuclear power plants (NPPs) are being designed utilizing computer-based technologies. The US Nuclear Regulatory Commission reviews the human engineering aspects of such control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported in order to protect public health and safety. This paper describes the rationale and general approach to the development of a human factors review guideline for ACRs. The factors influencing the guideline development are discussed, including the review environment, the types of advanced technologies being addressed, the human factors issues associated with advanced technology, and the current state-of-the-art of human factors guidelines for advanced human-system interfaces (HSIs). The proposed approach to ACR review would track the design and implementation process through the application of review guidelines reflecting four review modules: planning, design process analysis, human factors engineering review, and dynamic performance evaluation. 21 refs

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

    International Nuclear Information System (INIS)

    Rezniczek, A.

    2013-01-01

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

  20. Current status of process monitoring for IAEA safeguards

    International Nuclear Information System (INIS)

    Koroyasu, M.

    1987-06-01

    Based on literature survey, this report tries to answer some of the following questions on process monitoring for safeguards purposes of future large scale reprocessing plants: what is process monitoring, what are the basic elements of process monitoring, what kinds of process monitoring are there, what are the basic problems of process monitoring, what is the relationship between process monitoring and near-real-time materials accountancy, what are actual results of process monitoring tests and what should be studied in future. A brief description of Advanced Safeguards Approaches proposed by the four states (France, U.K., Japan and U.S.A.), the approach proposed by the U.S.A., the description of the process monitoring, the main part of the report published as a result of one of the U.S. Support Programmes for IAEA Safeguards and an article on process monitoring presented at an IAEA Symposium held in November 1986 are given in the annexes. 24 refs, 20 figs, tabs

  1. 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.

  2. Review of potential technology contributions to safeguards

    International Nuclear Information System (INIS)

    Sellers, T.A.

    1977-01-01

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

  3. 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

  4. 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)

  5. Evolution of safeguards systems design

    International Nuclear Information System (INIS)

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

    1979-01-01

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

  6. Safeguards effectiveness evaluations in safeguards planning

    International Nuclear Information System (INIS)

    Al-Ayat, R.A.

    1987-01-01

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

  7. 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.

  8. IAEA safeguard system

    International Nuclear Information System (INIS)

    Pontes, B.C.

    1987-01-01

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

  9. 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.

  10. 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)

  11. 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.

  12. Advanced approaches to failure mode and effect analysis (FMEA applications

    Directory of Open Access Journals (Sweden)

    D. Vykydal

    2015-10-01

    Full Text Available The present paper explores advanced approaches to the FMEA method (Failure Mode and Effect Analysis which take into account the costs associated with occurrence of failures during the manufacture of a product. Different approaches are demonstrated using an example FMEA application to production of drawn wire. Their purpose is to determine risk levels, while taking account of the above-mentioned costs. Finally, the resulting priority levels are compared for developing actions mitigating the risks.

  13. Safeguards Envelope Progress FY10

    International Nuclear Information System (INIS)

    Metcalf, Richard

    2010-01-01

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

  14. Safeguards Implementation in Kazakhstan: Experience and Challenges

    International Nuclear Information System (INIS)

    Zhantikin, T.

    2015-01-01

    Experience of Kazakhstan joined the NPT in 1993, just after desintegration of USSR, and enforced Safeguards Agreement in 1995 can be interesting in implementation of safeguards in non-standard cases. Having weapon materials and test infrastructure legacy, the country together with IAEA and several donor countries found acceptable approaches to meet NPT provisions. One of challenges was to provide protection of sensitive information that could be accidentally disclosed in safeguards activities. With support of several weapon countries in close cooperation with the IAEA Kazakhstan liquidated test infrastructure in Semipalatinsk, implemented projects on elimination and minimization of use of HEU in civil sector, decommissioning of BN-350 fast breeder reactor. Now the IAEA LEU Bank is going to be established in Kazakhstan, and more challenges are coming in implementation of safeguards. Some technical and organizational details will be described from the experience of Kazakhstan in these projects. (author)

  15. Advanced language modeling approaches, case study: Expert search

    NARCIS (Netherlands)

    Hiemstra, Djoerd

    2008-01-01

    This tutorial gives a clear and detailed overview of advanced language modeling approaches and tools, including the use of document priors, translation models, relevance models, parsimonious models and expectation maximization training. Expert search will be used as a case study to explain the

  16. Adapting advanced engineering design approaches to building design - potential benefits

    NARCIS (Netherlands)

    Hopfe, C.J.; Struck, C.; Hensen, J.L.M.; Böhms, M.

    2006-01-01

    A number of industries continuously progress advancing their design approaches based on the changing market constraints. Examples such as car, ship and airplane manufacturing industries utilize process setups and techniques, that differ significantly from the processes and techniques used by the

  17. Adapting advanced engineering design approaches to building design. Potential benefits

    NARCIS (Netherlands)

    Böhms, M.

    2006-01-01

    A number of industries continuously progress advancing their design approaches based on the changing market constraints. Examples such as car, ship and airplane manufacturing industries utilize process setups and techniques, that differ significantly from the processes and techniques used by the

  18. Advanced training course on state systems of accounting for and control of nuclear materials. Volume I. Program for technical assistance to IAEA safeguards

    International Nuclear Information System (INIS)

    Sorenson, R.J.; Schneider, R.A.

    1979-01-01

    Purpose of the course was to provide practical training in the implementation and operation of a national system of accounting for and control of nuclear materials in a bulk processing facility, in the context of international safeguards. This course extends the training received in the basic course on State Systems of Accounting for and Control of Nuclear Materials to a practical, illustrative example utilizing the Exxon Nuclear low enriched uranium fabrication plant. Volume I of this manual contains the text of the presentations following the outline of the syllabus. Sample problems and answers are also included, along with some visual aids

  19. Safeguarding the fuel cycle: Methodologies

    International Nuclear Information System (INIS)

    Gruemm, H.

    1984-01-01

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

  20. Safeguards needs in the measurement area: the realm of measurements

    International Nuclear Information System (INIS)

    Hammond, G.; Auerbach, C.

    1978-01-01

    An effective safeguards measurement system must cover a multitude of material forms ranging from essentially pure substances to highly heterogeneous materials. In addition there are varied and sometimes conflicting demands for accuracy and timeliness. Consequently, a judicious and systematic choice must be made between methods based on sampling followed by chemical analysis or nondestructive methods based on nuclear properties. Fundamental advances in analytical chemistry made during the year preceding World War II enabled Manhattan Project scientists to develop methods which contributed to the success of both the immediate goal and the developments which have taken place since. Examples are given of evolutionary developments in the direction of timeliness through varying degrees of automation. Nondestructive methods, first introduced because of the need to measure scrap and other intractable material, are finding broader areas of application. Aided by DOE-sponsored research and development, new techniques providing greater accuracy, versatility and timeliness are being introduced. It is now recognized that an effective safeguards measurement system must make concerted use of both chemical and nondestructive methods. Recent studies have fostered understanding of the relative importance of various process streams in the material balance equations and have highlighted the need for a systematic approach to measurement solutions for safeguarding nuclear materials

  1. 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.)

  2. 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

  3. 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

  4. Isotopic safeguards statistics

    International Nuclear Information System (INIS)

    Timmerman, C.L.; Stewart, K.B.

    1978-06-01

    The methods and results of our statistical analysis of isotopic data using isotopic safeguards techniques are illustrated using example data from the Yankee Rowe reactor. The statistical methods used in this analysis are the paired comparison and the regression analyses. A paired comparison results when a sample from a batch is analyzed by two different laboratories. Paired comparison techniques can be used with regression analysis to detect and identify outlier batches. The second analysis tool, linear regression, involves comparing various regression approaches. These approaches use two basic types of models: the intercept model (y = α + βx) and the initial point model [y - y 0 = β(x - x 0 )]. The intercept model fits strictly the exposure or burnup values of isotopic functions, while the initial point model utilizes the exposure values plus the initial or fabricator's data values in the regression analysis. Two fitting methods are applied to each of these models. These methods are: (1) the usual least squares fitting approach where x is measured without error, and (2) Deming's approach which uses the variance estimates obtained from the paired comparison results and considers x and y are both measured with error. The Yankee Rowe data were first measured by Nuclear Fuel Services (NFS) and remeasured by Nuclear Audit and Testing Company (NATCO). The ratio of Pu/U versus 235 D (in which 235 D is the amount of depleted 235 U expressed in weight percent) using actual numbers is the isotopic function illustrated. Statistical results using the Yankee Rowe data indicates the attractiveness of Deming's regression model over the usual approach by simple comparison of the given regression variances with the random variance from the paired comparison results

  5. Next Generation Safeguards Initiative: Human Capital Development

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  6. 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

  7. Strengthening regional safeguards

    International Nuclear Information System (INIS)

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

    1996-01-01

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

  8. Licensee safeguards contingency plans

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

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

  9. Part 7. Safeguards

    International Nuclear Information System (INIS)

    Amundson, P.I.; Rusch, G.K.

    1980-01-01

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

  10. Application of safeguards procedures

    International Nuclear Information System (INIS)

    1977-01-01

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

  11. 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'.

  12. Psychology of nuclear safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Parker, L [Manchester Univ. (UK)

    1978-08-17

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

  13. 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'

  14. 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.

  15. IAEA safeguards information system

    International Nuclear Information System (INIS)

    Nardi, J.

    1984-01-01

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

  16. 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

  17. Modeling and simulation for process and safeguards system design

    International Nuclear Information System (INIS)

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

    1983-01-01

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

  18. Methodology and preliminary models for analyzing nuclear safeguards decisions

    International Nuclear Information System (INIS)

    1978-11-01

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

  19. Comprehensive safeguards evaluation methods and societal risk analysis

    International Nuclear Information System (INIS)

    Richardson, J.M.

    1982-03-01

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

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

    International Nuclear Information System (INIS)

    Judd, B.R.; Weissenberger, S.

    1978-11-01

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

  1. 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.

  2. Safety, security and safeguard

    International Nuclear Information System (INIS)

    Zakariya, Nasiru Imam; Kahn, M.T.E.

    2015-01-01

    Highlights: • The 3S interface in the design of PPS is hereby proposed. • The 3S synergy enhances the reduction in vulnerability and terrorism. • Highlighted were concept of detection, delay and response. - Abstract: A physical protection system (PPS) integrates people, procedures, and equipment for the protection of assets or facilities against theft, sabotage and terrorist attacks. Therefore, this paper proposes the use of a systematic and measurable approach to the design of PPS and its emphases on the concept of detection, delay and response. The proposed performance based PPS has the capability of defeating adversaries thereby achieving its targets. Therefore, timely detection of intrusion – based on the use of sensors, signal lines and alarm systems – is a major principle in the proposed system. Also the need for deterrence such as barriers in form of guards, access control, close circuit television (CCTV), strong policy and procedures, then the security culture amongst the facility workers was appropriately discussed. Since nuclear power is considered the only source that can provide large scale electricity with comparatively minimal impact on the environment, the paper also considered base guidelines for the application of PPS in any nuclear and radioactive facilities, followed with the necessity to incorporate inherent safety, security and safeguard (3S) synergy innovation in the physical protection system design and other characteristics that will enhance to reduce the vulnerability of nuclear facilities and materials to theft sabotage and terrorist attacks

  3. Preauricular infratemporal fossa approach for advanced malignant parotid tumors.

    Science.gov (United States)

    Leonetti, John P; Benscoter, Brent J; Marzo, Sam J; Borrowdale, Richard W; Pontikis, George C

    2012-09-01

    The aims of this study were to demonstrate the surgical technique involved in the preauricular infratemporal fossa (ITF) approach, outline the clinical indications for use of this technique, and present the results in using this approach in 159 patients with malignant parotid tumors. At the conclusion of this article, the reader should be able to understand the utility of the preauricular infratemporal fossa approach in the management of patients with advanced malignant parotid tumors. This was a retrospective chart review of 159 patients treated at a tertiary care academic medical center following institutional review board approval. A comprehensive medical records review was performed for all patients with malignant parotid tumors who underwent a preauricular ITF approach between July 1988 and July 2010. The most common presenting symptoms were pain and trismus, whereas the presence of a parotid mass and facial paralysis were the most common clinical signs. Mucoepidermoid and adenoid cystic carcinoma accounted for 63% of the tumors, and perineural invasion was found in nearly 71% of the patients. Despite negative surgical margins in 92% of the patients, local or regional tumor recurrence was found in 17% of the cases. The mean follow-up time was 12.8 years. The preauricular ITF approach should be used in the surgical extirpation of advanced malignant parotid neoplasms. This technique provides proximal facial nerve identification, internal carotid artery protection, and negative tumor margins at the skull base. Copyright © 2012 The American Laryngological, Rhinological, and Otological Society, Inc.

  4. 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.

  5. Strengthened safeguards: Present and future challenges

    International Nuclear Information System (INIS)

    Goldschmidt, Pierre

    2001-01-01

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

  6. 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

  7. The development of safeguards for geological repositories

    International Nuclear Information System (INIS)

    Van der Meer, K.

    2009-01-01

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

  8. Computational experiment approach to advanced secondary mathematics curriculum

    CERN Document Server

    Abramovich, Sergei

    2014-01-01

    This book promotes the experimental mathematics approach in the context of secondary mathematics curriculum by exploring mathematical models depending on parameters that were typically considered advanced in the pre-digital education era. This approach, by drawing on the power of computers to perform numerical computations and graphical constructions, stimulates formal learning of mathematics through making sense of a computational experiment. It allows one (in the spirit of Freudenthal) to bridge serious mathematical content and contemporary teaching practice. In other words, the notion of teaching experiment can be extended to include a true mathematical experiment. When used appropriately, the approach creates conditions for collateral learning (in the spirit of Dewey) to occur including the development of skills important for engineering applications of mathematics. In the context of a mathematics teacher education program, this book addresses a call for the preparation of teachers capable of utilizing mo...

  9. 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.

  10. 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).

  11. 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).

  12. Safeguards systems parameters

    International Nuclear Information System (INIS)

    Avenhaus, R.; Heil, J.

    1979-01-01

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

  13. 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.

  14. 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)

  15. Reporting of safeguards events

    International Nuclear Information System (INIS)

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

    1988-02-01

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

  16. Building safeguards infrastructure

    International Nuclear Information System (INIS)

    McClelland-Kerr, J.; Stevens, J.

    2010-01-01

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

  17. Safeguarding arms control

    International Nuclear Information System (INIS)

    Flanagan, S.J.

    1988-01-01

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

  18. 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.

  19. 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

  20. The integration of process monitoring for safeguards

    International Nuclear Information System (INIS)

    Cipiti, Benjamin B.; Zinaman, Owen R.

    2010-01-01

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

  1. Safeguards management inspection procedures

    International Nuclear Information System (INIS)

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

    1984-08-01

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

  2. 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.

  3. 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

  4. 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

  5. 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

  6. 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

  7. 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

  8. Science based integrated approach to advanced nuclear fuel development - vision, approach, and overview

    Energy Technology Data Exchange (ETDEWEB)

    Unal, Cetin [Los Alamos National Laboratory; Pasamehmetoglu, Kemal [IDAHO NATIONAL LAB; Carmack, Jon [IDAHO NATIONAL LAB

    2010-01-01

    Advancing the performance of Light Water Reactors, Advanced Nuclear Fuel Cycles, and Advanced Rcactors, such as the Next Generation Nuclear Power Plants, requires enhancing our fundamental understanding of fuel and materials behavior under irradiation. The capability to accurately model the nuclear fuel systems is critical. In order to understand specific aspects of the nuclear fuel, fully coupled fuel simulation codes are required to achieve licensing of specific nuclear fuel designs for operation. The backbone of these codes, models, and simulations is a fundamental understanding and predictive capability for simulating the phase and microstructural behavior of the nuclear fuel system materials and matrices. The purpose of this paper is to identify the modeling and simulation approach in order to deliver predictive tools for advanced fuels development. The coordination between experimental nuclear fuel design, development technical experts, and computational fuel modeling and simulation technical experts is a critical aspect of the approach and naturally leads to an integrated, goal-oriented science-based R & D approach and strengthens both the experimental and computational efforts. The Advanced Fuels Campaign (AFC) and Nuclear Energy Advanced Modeling and Simulation (NEAMS) Fuels Integrated Performance and Safety Code (IPSC) are working together to determine experimental data and modeling needs. The primary objective of the NEAMS fuels IPSC project is to deliver a coupled, three-dimensional, predictive computational platform for modeling the fabrication and both normal and abnormal operation of nuclear fuel pins and assemblies, applicable to both existing and future reactor fuel designs. The science based program is pursuing the development of an integrated multi-scale and multi-physics modeling and simulation platform for nuclear fuels. This overview paper discusses the vision, goals and approaches how to develop and implement the new approach.

  9. Science based integrated approach to advanced nuclear fuel development - vision, approach, and overview

    International Nuclear Information System (INIS)

    Unal, Cetin; Pasamehmetoglu, Kemal; Carmack, Jon

    2010-01-01

    Advancing the performance of Light Water Reactors, Advanced Nuclear Fuel Cycles, and Advanced Rcactors, such as the Next Generation Nuclear Power Plants, requires enhancing our fundamental understanding of fuel and materials behavior under irradiation. The capability to accurately model the nuclear fuel systems is critical. In order to understand specific aspects of the nuclear fuel, fully coupled fuel simulation codes are required to achieve licensing of specific nuclear fuel designs for operation. The backbone of these codes, models, and simulations is a fundamental understanding and predictive capability for simulating the phase and microstructural behavior of the nuclear fuel system materials and matrices. The purpose of this paper is to identify the modeling and simulation approach in order to deliver predictive tools for advanced fuels development. The coordination between experimental nuclear fuel design, development technical experts, and computational fuel modeling and simulation technical experts is a critical aspect of the approach and naturally leads to an integrated, goal-oriented science-based R and D approach and strengthens both the experimental and computational efforts. The Advanced Fuels Campaign (AFC) and Nuclear Energy Advanced Modeling and Simulation (NEAMS) Fuels Integrated Performance and Safety Code (IPSC) are working together to determine experimental data and modeling needs. The primary objective of the NEAMS fuels IPSC project is to deliver a coupled, three-dimensional, predictive computational platform for modeling the fabrication and both normal and abnormal operation of nuclear fuel pins and assemblies, applicable to both existing and future reactor fuel designs. The science based program is pursuing the development of an integrated multi-scale and multi-physics modeling and simulation platform for nuclear fuels. This overview paper discusses the vision, goals and approaches how to develop and implement the new approach.

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

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  11. 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

  12. 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

  13. Separations and safeguards model integration.

    Energy Technology Data Exchange (ETDEWEB)

    Cipiti, Benjamin B.; Zinaman, Owen

    2010-09-01

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

  14. Advanced multiresponse process optimisation an intelligent and integrated approach

    CERN Document Server

    Šibalija, Tatjana V

    2016-01-01

    This book presents an intelligent, integrated, problem-independent method for multiresponse process optimization. In contrast to traditional approaches, the idea of this method is to provide a unique model for the optimization of various processes, without imposition of assumptions relating to the type of process, the type and number of process parameters and responses, or interdependences among them. The presented method for experimental design of processes with multiple correlated responses is composed of three modules: an expert system that selects the experimental plan based on the orthogonal arrays; the factor effects approach, which performs processing of experimental data based on Taguchi’s quality loss function and multivariate statistical methods; and process modeling and optimization based on artificial neural networks and metaheuristic optimization algorithms. The implementation is demonstrated using four case studies relating to high-tech industries and advanced, non-conventional processes.

  15. The advanced neutron source safety approach and plans

    International Nuclear Information System (INIS)

    Harrington, R.M.

    1989-01-01

    The Advanced Neutron Source (ANS) is a user facility for all areas of neutron research proposed for construction at the Oak Ridge National Laboratory. The neutron source is planned to be a 350-MW research reactor. The reactor, currently in conceptual design, will belong to the United States Department of Energy (USDOE). The safety approach and planned elements of the safety program for the ANS are described. The safety approach is to incorporate USDOE requirements [which, by reference, include appropriate requirements from the United States Nuclear Regulatory Commission (USNRC) and other national and state regulatory agencies] into the design, and to utilize probabilistic risk assessment (PRA) techniques during design to achieve extremely low probability of severe core damage. The PRA has already begun and will continue throughout the design and construction of the reactor. Computer analyses will be conducted for a complete spectrum of accidental events, from anticipated events to very infrequent occurrences. 8 refs., 2 tabs

  16. The Advanced Neutron Source safety approach and plans

    International Nuclear Information System (INIS)

    Harrington, R.M.

    1990-01-01

    The Advanced Neutron Source (ANS) is a user facility proposed for construction at the Oak Ridge National Laboratory for all areas of neutron research. The neutron source is planned to be a 350-MW research reactor. The reactor, currently in conceptual design, will belong to the United States Department of Energy (USDOE). The safety approach and planned elements of the safety program for the ANS are described. The safety approach is to incorporate USDOE requirements (which, by reference, include appropriate requirements from the United States Nuclear Regulatory Commission (USNRC) and other national and state regulatory agencies) into the design, and to utilize probabilistic risk assessment (PRA) techniques during design to achieve extremely low probability of severe core damage. The PRA has already begun and will continue throughout the design and construction of the reactor. Computer analyses will be conducted for a complete spectrum of accidental events, from anticipated events to very infrequent occurrences

  17. 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

  18. The Agency's Safeguards System (1965)

    International Nuclear Information System (INIS)

    1965-01-01

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

  19. 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)

  20. 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.

  1. Advanced Approach of Reactor Pressure Vessel In-service Inspection

    International Nuclear Information System (INIS)

    Matokovic, A.; Picek, E.; Pajnic, M.

    2006-01-01

    The most important task of every utility operating a nuclear power plant is the continuously keeping of the desired safety and reliability level. This is achieved by the performance of numerous inspections of the components, equipment and system of the nuclear power plant in operation and in particular during the scheduled maintenance periods at re-fueling time. Periodic non-destructive in-service inspections provide most relevant criteria of the integrity of primary circuit pressure components. The task is to reliably detect defects and realistically size and characterize them. One of most important and the most extensive examination is a reactor pressure vessel in-service inspection. That inspection demand high standards of technology and quality and continual innovation in the field of non-destructive testing (NDT) advanced technology as well as regarding reactor pressure vessel tool and control systems. A remote underwater contact ultrasonic technique is employed for the examination of the defined sections (reactor welds), whence eddy current method is applied for clad surface examinations. Visual inspection is used for examination of the vessel inner surface. The movement of probes and data positioning are assured by using new reactor pressure vessel tool concept that is fully integrated with NDT systems. The successful performance is attributed thorough pre-outage planning, training and successful performance demonstration qualification of chosen NDT techniques on the specimens with artificial and/or real defects. Furthermore, use of advanced approach of inspection through implementation the state of the art examination equipment significantly reduced the inspection time, radiation exposure to examination personnel, shortening nuclear power plant outage and cutting the total inspection costs. The advanced approach as presented in this paper offer more flexibility of application (non-destructive tests, local grinding action as well as taking of boat samples

  2. The evolution of safeguards

    International Nuclear Information System (INIS)

    Heinonen, O.

    1999-01-01

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

  3. Safeguards system design methodology

    International Nuclear Information System (INIS)

    Cravens, M.N.; Winblad, A.E.

    1977-01-01

    Sandia Laboratories is developing methods for the design of physical protection systems to safeguard special nuclear material and vital equipment at fixed sites. One method is outlined and illustrated with simplified examples drawn from current programs. The use of an adversary sequence diagram as an analysis tool is discussed

  4. Technical basis of safeguards

    International Nuclear Information System (INIS)

    Buechler, C.

    1975-01-01

    Definition of nuclear materials control. Materials accountancy and physical control as technical possibilities. Legal possibilities and levels of responsibility: material holders, national and international authority. Detection vs. prevention. Physical security and containment surveillance. Accountancy: materials balance concept. Materials measurement: inventory taking, flow determination. IAEA safeguards; verification of operator's statement. (HP) [de

  5. Nuclear safeguards project

    International Nuclear Information System (INIS)

    Mache, H.R.

    1978-10-01

    The present report describes the major activities carried out in 1977 in the framework of the Nuclear Safeguards Project by the institutes of the Kernforschungszentrum Karlsruhe, Kernforschungsanlage Juelich, the European Institute of Transuranium Elements and some industrial firms. (orig.) 891 HP 892 AP [de

  6. Safeguards techniques and equipment

    International Nuclear Information System (INIS)

    1997-01-01

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

  7. IAEA safeguards technical manual

    International Nuclear Information System (INIS)

    1982-03-01

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

  8. 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

  9. Brazilian reactors under safeguards

    International Nuclear Information System (INIS)

    1967-01-01

    Three nuclear reactors in Brazil have been placed under Agency safeguards against diversion to military use. They are used for research purposes under a bilateral treaty with the USA, and are located at Rio de Janeiro, Sao Paulo and Belo Horizonte

  10. 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

  11. Safeguards Implementation Practices Guide on Facilitating IAEA Verification Activities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-12-15

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

  12. Safeguards Implementation Practices Guide on Facilitating IAEA Verification Activities

    International Nuclear Information System (INIS)

    2014-01-01

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

  13. Application of safeguards technology in DOE's environmental restoration program

    International Nuclear Information System (INIS)

    Eccleston, G.W.; Baker, M.P.; Hansen, W.R.; Lucas, M.C.; Markin, J.T.; Phillips, J.R.

    1990-01-01

    During the last two decades, the Department of Energy's Office of Safeguards and Security (DOE/OSS) has supported the research and development of safeguards systems analysis methodologies and nondestructive assay (NDS) technology for characterizing, monitoring, and accounting nuclear materials. This paper discusses methodologies and NDA instrumentation developed by the DOE/OSS program that could be applied in the Environmental Restoration Program. NDA instrumentation could be used for field measurements during site characterization and to monitor nuclear materials, heavy metals, and other hazardous materials during site remediation. Systems methodologies can minimize the expenditure of resources and help specify appropriate combinations of NDA instrumentation and chemical analyses to characterize a variety of materials quickly and reduce personnel exposure in hazardous environments. A training program is available to teach fundamental and advanced principles and approaches to characterize and quantify nuclear materials properly and to organize and analyze measurement information for decision making. The ability to characterize the overall volume and distribution of materials at a waste site is difficult because of the inhomogeneous distribution of materials, the requirement for extreme sensitivity, and the lack of resources to collect and chemically analyze a sufficient number of samples. Using a systems study approach based on statistical sampling, the resources necessary to characterize a site can be enhanced by appropriately combining in situ and field NDA measurements with laboratory analyses. 35 refs., 1 figs., 2 tabs

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

    International Nuclear Information System (INIS)

    Gyane, E.

    2010-01-01

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

  15. Safeguarding a future industrial reprocessing plant

    International Nuclear Information System (INIS)

    1978-11-01

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

  16. Working Group 2: Future Directions for Safeguards and Verification, Technology, Research and Development

    International Nuclear Information System (INIS)

    Zykov, S.; Blair, D.

    2013-01-01

    For traditional safeguards it was recognized that the hardware presently available is, in general, addressing adequately fundamental IAEA needs, and that further developments should therefore focus mainly on improving efficiencies (i.e. increasing cost economies, reliability, maintainability and user-friendliness, keeping abreast of continual advancements in technologies and of the evolution of verification approaches). Specific technology areas that could benefit from further development include: -) Non-destructive measurement systems (NDA), in particular, gamma-spectroscopy and neutron counting techniques; -) Containment and surveillance tools, such as tamper indicating seals, video-surveillance, surface identification methods, etc.; -) Geophysical methods for design information verification (DIV) and safeguarding of geological repositories; and -) New tools and methods for real-time monitoring. Furthermore, the Working Group acknowledged that a 'building block' (or modular) approach should be adopted towards technology development, enabling equipment to be upgraded efficiently as technologies advance. Concerning non-traditional safeguards, in the area of satellite-based sensors, increased spatial resolution and broadened spectral range were identified as priorities. In the area of wide area surveillance, the development of LIDAR-like tools for atmospheric sensing was discussed from the perspective of both potential benefits and certain limitations. Recognizing the limitations imposed by the human brain in terms of information assessment and analysis, technologies are needed that will enable the more effective utilization of all information, regardless of its format and origin. The paper is followed by the slides of the presentation. (A.C.)

  17. 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

  18. 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

  19. 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

  20. 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.

  1. 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.

  2. 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)

  3. 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)

  4. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Mark Schanfein; Shirley Johnson

    2012-02-01

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

  6. The Integrated Approach to the Accident Evaluation for Advanced LWRs

    International Nuclear Information System (INIS)

    Oriolo, F.; Paci, S.

    1998-01-01

    The present paper discusses some relevant phenomena occurring in advanced LWRs during postulated accident scenarios. In particular, the operation of ESF is the starting point for analysis of those phenomena that cause the mutual influence between PS and containment in these plants. As a consequence, it is highlighted as accident analyses which treat PS and containment phenomena completely separated may be not adequate when applied to innovate reactors. Exemplified thermal-hydraulic analysis are presented for AP600 and SBWR, using the FUMO integrated model, for highlight accident evolution taking into account these interactions. The architecture of this integrated code is presented highlighting the importance of an integrated approach to the safety analysis in innovative reactors. (author)

  7. Closely approaching advanced age in a supermax prison.

    Science.gov (United States)

    Lynd, Staughton

    2014-01-01

    When a Social Security recipient reaches the age of 50 years, he or she is classified as "closely approaching advanced age." Todd Ashker is passing this tipping point at Pelican Bay State Prison in California, a supermaximum security facility. My wife and I have corresponded with Mr. Ashker for more than half a dozen years. Although I cannot verify the details of his account, we believe that his representation of facts is generally reliable. He is one of the spokespersons for prisoners who conducted two hunger strikes in 2011 protesting conditions of their confinement. Another, sixty-day hunger strike took place in 2013. Thus, what follows is a story of resilience as well as victimization.

  8. India and the nuclear safeguards controversy

    International Nuclear Information System (INIS)

    Poulose, T.T.

    1979-01-01

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

  9. 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

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

    International Nuclear Information System (INIS)

    Boozer, D.D.; Engi, D.

    1977-04-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Boozer, D.D.; Engi, D.

    1977-04-01

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

  12. Information collection strategies to support strengthened safeguards

    International Nuclear Information System (INIS)

    Costantini, L.; Hill, J.

    2001-01-01

    The IAEA Board of Governors approved the implementation of Part 1 of Strengthened Safeguards in June 1995. Since then, the collection and analysis of information beyond that provided by States parties and acquired by inspectors under NPT Safeguards Agreements has been an integral part of IAEA safeguards. The Agency has formally established internal structures and procedures to facilitate the effective use of open-source and other information not previously used in safeguards. Over this period the IAEA Division of Safeguards Information Technology (SGIT) has been building its collections of electronically held open source information. Some of these collections are quite nuclear-specific, such as material from the Monterey Institute in California, and nuclear news collections provided voluntarily by a number of Member States. Others are completely general news sources. Several of these collections contain many more reports than could possibly be reviewed by a human analyst. So a need has arisen for computerised search facilities to identify nuclear-relevant items from those collections. The Agency has more than one piece of software available to help searching and analysis of substantial collections of reports. Search 97 from Verity was chosen for this particular application because it is very straightforward to use, and it was expected that personnel from all over the Department of Safeguards would carry out these searches on a routine basis. The approach whereby special-purpose search mechanisms are designed for use by a large number of users, who are unfamiliar with the details of the search software, seems to be unusual if not unique to the Agency

  13. Safeguards Evaluation Method for evaluating vulnerability to insider threats

    International Nuclear Information System (INIS)

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

    1986-01-01

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

  14. 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.

  15. Safeguards technology research and development at CIAE

    International Nuclear Information System (INIS)

    Yang Qun

    2001-01-01

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

  16. Networking of safeguards systems

    International Nuclear Information System (INIS)

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

    1995-01-01

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

  17. IAEA Safeguards: Status and prospects

    International Nuclear Information System (INIS)

    Gruemm, H.

    1983-01-01

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

  18. Keeping all options open: Parents' approaches to advance care planning.

    Science.gov (United States)

    Beecham, Emma; Oostendorp, Linda; Crocker, Joanna; Kelly, Paula; Dinsdale, Andrew; Hemsley, June; Russell, Jessica; Jones, Louise; Bluebond-Langner, Myra

    2017-08-01

    Early engagement in advance care planning (ACP) is seen as fundamental for ensuring the highest standard of care for children and young people with a life-limiting condition (LLC). However, most families have little knowledge or experience of ACP. To investigate how parents of children and young people with LLCs approach and experience ACP. Open-ended, semi-structured interviews were conducted with parents of 18 children; nine children who were currently receiving palliative care services, and nine children who had received palliative care and died. Verbatim transcripts of audiotaped interviews were analysed following principles of grounded theory while acknowledging the use of deductive strategies, taking account of both the child's condition, and the timing and nature of decisions made. Parents reported having discussions and making decisions about the place of care, place of death and the limitation of treatment. Most decisions were made relatively late in the illness and by parents who wished to keep their options open. Parents reported different levels of involvement in a range of decisions; many wished to be involved in decision making but did not always feel able to do so. This study highlights that parents' approaches to decision making vary by the type of decision required. Their views may change over time, and it is important to allow them to keep their options open. We recommend that clinicians have regular discussions over the course of the illness in an effort to understand parents' approaches to particular decisions rather than to drive to closure prematurely. © 2016 The Authors Health Expectations Published by John Wiley & Sons Ltd.

  19. Safeguarding research reactors

    International Nuclear Information System (INIS)

    Powers, J.A.

    1983-03-01

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

  20. Safeguards for the atom

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1959-10-15

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

  1. Safeguards for the atom

    International Nuclear Information System (INIS)

    1959-01-01

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

  2. Introduction of designated organization to safeguards implementation in Japan

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  3. Computer-based safeguards information and accounting system

    International Nuclear Information System (INIS)

    1977-01-01

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

  4. IAEA's Safeguards Implementation Practices Guides

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  5. Authentication method for safeguards instruments securing data transmission

    International Nuclear Information System (INIS)

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

    1986-01-01

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

  6. Safeguards operations in the integral fast reactor fuel cycle

    International Nuclear Information System (INIS)

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

    1994-01-01

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

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

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  8. 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.

  9. 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

  10. Validation of safeguards monitoring systems and their simulations

    International Nuclear Information System (INIS)

    Standley, V.; Boeck, H.; Villa, M.

    2001-01-01

    Research is underway at the Atominstitut in Vienna Austria where the objective is to design and validate quantitatively a safeguards monitoring system (SMS) and its simulation. The work is novel because the simulation is also used as the basis for automated evaluation of SMS data. Preliminary results indicate that video and radiation data can be automatically interpreted using this approach. Application of the technique promises that an investment in a simulation supports directly the safeguards objective, which is to catch diversion of nuclear material. Consequently, it is easier for a safeguards agency to also realize other benefits associated with simulation-based acquisition, in addition to having a quantitative method for validation

  11. IAEA Safeguards Information System (ISIS)

    International Nuclear Information System (INIS)

    1984-10-01

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

  12. Defining and Measuring Safeguards Culture

    International Nuclear Information System (INIS)

    Frazar, Sarah L.; Mladineo, Stephen V.

    2010-01-01

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

  13. IAEA safeguards - a 1988 perspective

    International Nuclear Information System (INIS)

    Jennekens, J.

    1988-01-01

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

  14. Nuclear safeguards - a system in transition

    International Nuclear Information System (INIS)

    Carlson, J.

    1999-01-01

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

  15. Strengthening IAEA Safeguards for Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-09-01

    During their December 10-11, 2013, workshop in Grenoble France, which focused on the history and future of safeguarding research reactors, the United States, France and the United Kingdom (UK) agreed to conduct a joint study exploring ways to strengthen the IAEA’s safeguards approach for declared research reactors. This decision was prompted by concerns about: 1) historical cases of non-compliance involving misuse (including the use of non-nuclear materials for production of neutron generators for weapons) and diversion that were discovered, in many cases, long after the violations took place and as part of broader pattern of undeclared activities in half a dozen countries; 2) the fact that, under the Safeguards Criteria, the IAEA inspects some reactors (e.g., those with power levels under 25 MWt) less than once per year; 3) the long-standing precedent of States using heavy water research reactors (HWRR) to produce plutonium for weapons programs; 4) the use of HEU fuel in some research reactors; and 5) various technical characteristics common to some types of research reactors that could provide an opportunity for potential proliferators to misuse the facility or divert material with low probability of detection by the IAEA. In some research reactors it is difficult to detect diversion or undeclared irradiation. In addition, infrastructure associated with research reactors could pose a safeguards challenge. To strengthen the effectiveness of safeguards at the State level, this paper advocates that the IAEA consider ways to focus additional attention and broaden its safeguards toolbox for research reactors. This increase in focus on the research reactors could begin with the recognition that the research reactor (of any size) could be a common path element on a large number of technically plausible pathways that must be considered when performing acquisition pathway analysis (APA) for developing a State Level Approach (SLA) and Annual Implementation Plan (AIP). To

  16. Oxidative Stress in Aging: Advances in Proteomic Approaches

    Directory of Open Access Journals (Sweden)

    Daniel Ortuño-Sahagún

    2014-01-01

    Full Text Available Aging is a gradual, complex process in which cells, tissues, organs, and the whole organism itself deteriorate in a progressive and irreversible manner that, in the majority of cases, implies pathological conditions that affect the individual’s Quality of Life (QOL. Although extensive research efforts in recent years have been made, the anticipation of aging and prophylactic or treatment strategies continue to experience major limitations. In this review, the focus is essentially on the compilation of the advances generated by cellular expression profile analysis through proteomics studies (two-dimensional [2D] electrophoresis and mass spectrometry [MS], which are currently used as an integral approach to study the aging process. Additionally, the relevance of the oxidative stress factors is discussed. Emphasis is placed on postmitotic tissues, such as neuronal, muscular, and red blood cells, which appear to be those most frequently studied with respect to aging. Additionally, models for the study of aging are discussed in a number of organisms, such as Caenorhabditis elegans, senescence-accelerated probe-8 mice (SAMP8, naked mole-rat (Heterocephalus glaber, and the beagle canine. Proteomic studies in specific tissues and organisms have revealed the extensive involvement of reactive oxygen species (ROS and oxidative stress in aging.

  17. Safeguard Vulnerability Analysis Program (SVAP)

    International Nuclear Information System (INIS)

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

    1980-01-01

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

  18. Safeguards Knowledge Management & Retention at U.S. National Laboratories.

    Energy Technology Data Exchange (ETDEWEB)

    Haddal, Risa [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Jones, Rebecca [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Bersell, Bridget [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Frazar, Sarah [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Burbank, Roberta [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Stevens, Rebecca [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Cain, Ron [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Kirk, Bernadette [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Morell, Sean [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2017-09-01

    In 2017, four U.S. National Laboratories collaborated on behalf of DOE/NNSA to explore the safeguards knowledge retention problem, identify possible approaches, and develop a strategy to address it. The one-year effort consisted of four primary tasks. First, the project sought to identify critical safeguards information at risk of loss. Second, a survey and workshop were conducted to assess nine U.S. National Laboratories' efforts to determine current safeguards knowledge retention practices and challenges, and identify best practices. Third, specific tools were developed to identify and predict critical safeguards knowledge gaps and how best to recruit in order to fill those gaps. Finally, based on findings from the first three tasks and research on other organizational approaches to address similar issues, a strategy was developed on potential knowledge retention methods, customized HR policies, and best practices that could be implemented across the National Laboratory Complex.

  19. 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)

  20. 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

  1. Neutron techniques in Safeguards

    International Nuclear Information System (INIS)

    Zucker, M.S.

    1982-01-01

    An essential part of Safeguards is the ability to quantitatively and nondestructively assay those materials with special neutron-interactive properties involved in nuclear industrial or military technology. Neutron techniques have furnished most of the important ways of assaying such materials, which is no surprise since the neutronic properties are what characterizes them. The techniques employed rely on a wide selection of the many methods of neutron generation, detection, and data analysis that have been developed for neutron physics and nuclear science in general

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

    International Nuclear Information System (INIS)

    1999-01-01

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

  3. 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

  4. 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.

  5. 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

  6. Safeguards as Design Criteria - Guidance for Regulators

    International Nuclear Information System (INIS)

    Leask, Andrew; Leslie, Russell; Carlson, John

    2004-01-01

    This paper examines some technological barriers which should be taken into account at the conceptual stage of fuel cycle design. First, the strategic value of nuclear material and reactor-associated fissile material acquisition paths is briefly outlined. Then, it discusses three basic approaches to enhance the proliferation resistance of nuclear power reactors, namely: (1) reduction of strategic value of materials involved in nuclear power generation; (2) incorporating reactor design features preventing diversion of material; and (3) facilitating safeguards implementation. (author)

  7. Exploratory study on potential safeguards applications for shared ledger technology

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-02-07

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

  8. 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

  9. 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

  10. Strengthening safeguards information evaluation

    International Nuclear Information System (INIS)

    Harry, J.; Hudson, P.

    2001-01-01

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

  11. 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

  12. 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

  13. IAEA safeguards glossary. 2001 ed

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-06-01

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

  14. IAEA safeguards glossary. 2001 ed

    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

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

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  16. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-10-15

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

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

    International Nuclear Information System (INIS)

    Lee, Haneol; Yim, Man-Sung

    2016-01-01

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

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

    International Nuclear Information System (INIS)

    Park, Seung Sik

    1999-01-01

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

  20. Technological developments and safeguards instrumentation: Responding to new challenges

    International Nuclear Information System (INIS)

    Naito, K.; Rundquist, D.E.

    1994-01-01

    Entering the 1990s, technological tools that were in the research and development stage not so long ago are changing the way inspectors are able to verify nuclear materials at many facilities around the world. Many new instruments - ranging from advanced video monitoring systems to miniature detectors and analysers - already are in place. In some cases, they have been custom-made for specific safeguards tasks, or for placement in locations, such as underwater storage pools for spent reactor fuel, where inspectors cannot go. Standing behind the development of many of these new safeguards instruments are a number of factors. They include: technological advances In computer related fields, such as microprocessing and electronics, and specific areas of instrumentation; technical developments in the nuclear industry and Efficiency improvements and efforts to reduce the costs of safeguards implementation

  1. Advanced approaches to high intensity laser-driven ion acceleration

    International Nuclear Information System (INIS)

    Henig, Andreas

    2010-01-01

    Since the pioneering work that was carried out 10 years ago, the generation of highly energetic ion beams from laser-plasma interactions has been investigated in much detail in the regime of target normal sheath acceleration (TNSA). Creation of ion beams with small longitudinal and transverse emittance and energies extending up to tens of MeV fueled visions of compact, laser-driven ion sources for applications such as ion beam therapy of tumors or fast ignition inertial con finement fusion. However, new pathways are of crucial importance to push the current limits of laser-generated ion beams further towards parameters necessary for those applications. The presented PhD work was intended to develop and explore advanced approaches to high intensity laser-driven ion acceleration that reach beyond TNSA. In this spirit, ion acceleration from two novel target systems was investigated, namely mass-limited microspheres and nm-thin, free-standing diamond-like carbon (DLC) foils. Using such ultrathin foils, a new regime of ion acceleration was found where the laser transfers energy to all electrons located within the focal volume. While for TNSA the accelerating electric field is stationary and ion acceleration is spatially separated from laser absorption into electrons, now a localized longitudinal field enhancement is present that co-propagates with the ions as the accompanying laser pulse pushes the electrons forward. Unprecedented maximum ion energies were obtained, reaching beyond 0.5 GeV for carbon C 6+ and thus exceeding previous TNSA results by about one order of magnitude. When changing the laser polarization to circular, electron heating and expansion were shown to be efficiently suppressed, resulting for the first time in a phase-stable acceleration that is dominated by the laser radiation pressure which led to the observation of a peaked C 6+ spectrum. Compared to quasi-monoenergetic ion beam generation within the TNSA regime, a more than 40 times increase in

  2. Advanced approaches to high intensity laser-driven ion acceleration

    Energy Technology Data Exchange (ETDEWEB)

    Henig, Andreas

    2010-04-26

    Since the pioneering work that was carried out 10 years ago, the generation of highly energetic ion beams from laser-plasma interactions has been investigated in much detail in the regime of target normal sheath acceleration (TNSA). Creation of ion beams with small longitudinal and transverse emittance and energies extending up to tens of MeV fueled visions of compact, laser-driven ion sources for applications such as ion beam therapy of tumors or fast ignition inertial con finement fusion. However, new pathways are of crucial importance to push the current limits of laser-generated ion beams further towards parameters necessary for those applications. The presented PhD work was intended to develop and explore advanced approaches to high intensity laser-driven ion acceleration that reach beyond TNSA. In this spirit, ion acceleration from two novel target systems was investigated, namely mass-limited microspheres and nm-thin, free-standing diamond-like carbon (DLC) foils. Using such ultrathin foils, a new regime of ion acceleration was found where the laser transfers energy to all electrons located within the focal volume. While for TNSA the accelerating electric field is stationary and ion acceleration is spatially separated from laser absorption into electrons, now a localized longitudinal field enhancement is present that co-propagates with the ions as the accompanying laser pulse pushes the electrons forward. Unprecedented maximum ion energies were obtained, reaching beyond 0.5 GeV for carbon C{sup 6+} and thus exceeding previous TNSA results by about one order of magnitude. When changing the laser polarization to circular, electron heating and expansion were shown to be efficiently suppressed, resulting for the first time in a phase-stable acceleration that is dominated by the laser radiation pressure which led to the observation of a peaked C{sup 6+} spectrum. Compared to quasi-monoenergetic ion beam generation within the TNSA regime, a more than 40 times

  3. 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

  4. Advanced Time Approach of FW-H Equations for Predicting Noise

    DEFF Research Database (Denmark)

    Haiqing, Si; Yan, Shi; Shen, Wen Zhong

    2013-01-01

    An advanced time approach of Ffowcs Williams-Hawkings (FW-H) acoustic analogy is developed, and the integral equations and integral solution of FW-H acoustic analogy are derived. Compared with the retarded time approach, the transcendental equation need not to be solved in the advanced time...

  5. 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

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

    International Nuclear Information System (INIS)

    Haginoya, Tohru

    1997-01-01

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

  7. Los Alamos safeguards program overview and NDA in safeguards

    International Nuclear Information System (INIS)

    Keepin, G.R.

    1988-01-01

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

  8. A Grounded Theory Approach to Physical Activity and Advanced Cancer

    Directory of Open Access Journals (Sweden)

    Sonya S. Lowe

    2015-11-01

    Full Text Available Background: Physical activity has demonstrated benefits in cancer-related fatigue and physical functioning in early-stage cancer patients, however the role of physical activity at the end stage of cancer has not been established. To challenge positivist–empiricist assumptions, I am seeking to develop a new theoretical framework that is grounded in the advanced cancer patient’s experience of activity. Aim: To gain an in-depth understanding of the experience of activity and quality of life in advanced cancer patients. Objectives: (1 To explore the meaning of activity for advanced cancer patients in the context of their day-to-day life, (2 to elicit advanced cancer patients’ perceptions of activity with respect to their quality of life, and (3 to elicit advanced cancer patients’ views of barriers and facilitators to activity in the context of their day-to-day life. Study Design: A two-phase, cross-sectional, qualitative study will be conducted through the postpositivist lens of subtle realism and informed by the principles of grounded theory methods. Study Methods: Advanced cancer patients will be recruited through the outpatient department of a tertiary cancer center. For Phase one, participants will wear an activPAL™ activity monitor and fill out a daily record sheet for seven days duration. For Phase two, the activity monitor output and daily record sheets will be used as qualitative probes for face-to-face, semistructured interviews. Concurrent coding, constant comparative analysis, and theoretical sampling will continue with the aim of achieving as close as possible to theoretical saturation. Ethics and Discussion: Ethical and scientific approval will be obtained by all local institutional review boards prior to study commencement. The findings will generate new mid-level theory about the experience of activity and quality of life in advanced cancer patients and aid in the development of a new theoretical framework for designing

  9. Safeguards implementation in UP3 reprocessing plant

    International Nuclear Information System (INIS)

    Laurent, J.P.; Regnier, J.; Talbourdet, Y.; De Jong, P.

    1991-01-01

    The implementation of safeguards in a large size reprocessing plant is a challenge, considering the high throughput of nuclear material and the sophisticated automation of such facilities. In the case of UP3, a pragmatic and realistic approach has been devised and is applied through an efficient cooperation between the safeguards organizations, the french national authorities and the operator. In essence, they consist in verification of every significant inputs and outputs, in timely analysis by NDA (e.g. solutions of dissolution through an on site k-edge equipment), in monitoring selected parts of the inprocess inventory and in specific containment/surveillance systems for the spent fuel storage ponds and the PuO2 storage. (author)

  10. Implementation of Safeguards in Thailand

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  11. 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

  12. 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

  13. The Safeguard of Audio Collections: A Computer Science Based Approach to Quality Control—The Case of the Sound Archive of the Arena di Verona

    Directory of Open Access Journals (Sweden)

    Federica Bressan

    2013-01-01

    Full Text Available In the field of multimedia, very little attention is given to the activities involved in the preservation of audio documents. At the same time, more and more archives storing audio and video documents face the problem of obsolescing and degrading media, which could largely benefit from the instruments and the methodologies of research in multimedia. This paper presents the methodology and the results of the Italian project REVIVAL, aimed at the development of a hardware/software platform to support the active preservation of the audio collection of the Fondazione Arena di Verona, one of the finest in Europe for the operatic genre, with a special attention on protocols and tools for quality control. On the scientific side, the most significant objectives achieved by the project are (i the setup of a working environment inside the archive, (ii the knowledge transfer to the archival personnel, (iii the realization of chemical analyses on magnetic tapes in collaboration with experts in the fields of materials science and chemistry, and (iv the development of original open-source software tools. On the cultural side, the recovery, the safeguard, and the access to unique copies of unpublished live recordings of artists the calibre of Domingo and Pavarotti are of great musicological and economical value.

  14. Optimizing the integrated safeguards system: Pragmatism and fresh views are the keys to a viable system

    International Nuclear Information System (INIS)

    Albert, M.-G.

    2001-01-01

    evaluation of the State. Ensuring that verification activities are partly unpredictable, with respect to timing, location, and activities performed, is a strong deterrent and can lead to cost savings while maintaining a high level of assurance. Some level of unpredictability should thus be introduced in all aspects of verification. Complementary access is an essential feature of the new Safeguards System. Although it should not be used in a mechanistic fashion nor as a systematic prerequisite for Integrated Safeguards, it should take place whenever necessary, not only to ensure the effectiveness of safeguards, but also to maintain the possibility to have recourse to it. Needless to say, the Agency should also, in a pragmatic way, seize every technical opportunity to reduce costs, for instance through the use of advanced technology where it can provide savings, or through increased co-operation with Regional or State Systems of Accounting for and Control of Nuclear Material and controlled use of the results of their work. In conclusion, it should be tirelessly reiterated that the ultimate goal of the new system is stronger safeguards and increased assurances for the international community. And this will only be possible, especially in a context of financial constraints, through a pragmatic, goal- oriented, fresh and determined approach to the new rules that will make Integrated Safeguards effective, cost-effective and, in the end, viable

  15. Synergies across verification regimes: Nuclear safeguards and chemical weapons convention compliance

    International Nuclear Information System (INIS)

    Kadner, Steven P.; Turpen, Elizabeth

    2001-01-01

    In the implementation of all arms control agreements, accurate verification is essential. In setting a course for verifying compliance with a given treaty - whether the NPT or the CWC, one must make a technical comparison of existing information-gathering capabilities against the constraints in an agreement. Then it must be decided whether this level of verifiability is good enough. Generally, the policy standard of 'effective verification' includes the ability to detect significant violations, with high confidence, in sufficient time to respond effectively with policy adjustments or other responses, as needed. It is at this juncture where verification approaches have traditionally diverged. Nuclear safeguards requirements have taken one path while chemical verification methods have pursued another. However, recent technological advances have brought a number of changes affecting verification, and lately their pace has been accelerating. First, all verification regimes have more and better information as a result of new kinds of sensors, imagery, and other technologies. Second, the verification provisions in agreements have also advanced, to include on-site inspections, portal monitoring, data exchanges, and a variety of transparency, confidence-building, and other cooperative measures, Together these developments translate into a technological overlap of certain institutional verification measures such as the NPT's safeguards requirements and the IAEA and the CWC's verification visions and the OPCW. Hence, a priority of international treaty-implementing organizations is exploring the development of a synergistic and coordinated approach to WMD policy making that takes into account existing inter-linkages between nuclear, chemical, and biological weapons issues. Specific areas of coordination include harmonizing information systems and information exchanges and the shared application of scientific mechanisms, as well as collaboration on technological developments

  16. Safeguards summary event list (SSEL)

    International Nuclear Information System (INIS)

    1989-07-01

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

  17. Safeguards Summary Event List (SSEL)

    International Nuclear Information System (INIS)

    Fadden, M.; Yardumian, J.

    1993-07-01

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

  18. IAEA safeguards: Challenges and opportunities

    International Nuclear Information System (INIS)

    1993-01-01

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

  19. Some reflections on nuclear safeguards

    International Nuclear Information System (INIS)

    Campbell, Ross.

    1981-01-01

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

  20. An approach to the management of locally advanced breast cancer ...

    African Journals Online (AJOL)

    Locally advanced breast cancer (LABC) comprises a heterogeneous group of diseases. It incorporates a subset of stage IIB (T3N0) disease, stage III disease and inflammatory breast cancer. In the developed world, 7% of breast cancer patients have stage III disease at diagnosis. In developing countries, LABC constitutes ...

  1. Technology transfer - insider protection workshop (Safeguards Evaluation Method - Insider Threat)

    International Nuclear Information System (INIS)

    Strait, R.S.; Renis, T.A.

    1986-01-01

    The Safeguards Evaluation Method - Insider Threat, developed by Lawrence Livermore National Laboratory, is a field-applicable tool to evaluate facility safeguards against theft or diversion of special nuclear material (SNM) by nonviolent insiders. To ensure successful transfer of this technology from the laboratory to DOE field offices and contractors, LLNL developed a three-part package. The package includes a workbook, user-friendly microcomputer software, and a three-day training program. The workbook guides an evaluation team through the Safeguards Evaluation Method and provides forms for gathering data. The microcomputer software assists in the evaluation of safeguards effectiveness. The software is designed for safeguards analysts with no previous computer experience. It runs on an IBM Personal Computer or any compatible machine. The three-day training program is called the Insider Protection Workshop. The workshop students learn how to use the workbook and the computer software to assess insider vulnerabilities and to evaluate the benefits and costs of potential improvements. These activities increase the students' appreciation of the insider threat. The workshop format is informal and interactive, employing four different instruction modes: classroom presentations, small-group sessions, a practical exercise, and ''hands-on'' analysis using microcomputers. This approach to technology transfer has been successful: over 100 safeguards planners and analysts have been trained in the method, and it is being used at facilities through the DOE complex

  2. A technical analysis of the IAEA nuclear safeguards

    International Nuclear Information System (INIS)

    Yoon, J. W.

    1998-01-01

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

  3. Unattended safeguards instrumentation at centrifuge enrichment plants

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  4. Safeguards for special nuclear materials

    International Nuclear Information System (INIS)

    Carlson, R.L.

    1979-12-01

    Safeguards, accountability, and nuclear materials are defined. The accuracy of measuring nuclear materials is discussed. The use of computers in nuclear materials accounting is described. Measures taken to physically protect nuclear materials are described

  5. 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.)

  6. 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)

  7. Safeguards and Nuclear Material Management

    International Nuclear Information System (INIS)

    Stanchi, L.

    1991-01-01

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

  8. Advanced approaches to intelligent information and database systems

    CERN Document Server

    Boonjing, Veera; Chittayasothorn, Suphamit

    2014-01-01

    This book consists of 35 chapters presenting different theoretical and practical aspects of Intelligent Information and Database Systems. Nowadays both Intelligent and Database Systems are applied in most of the areas of human activities which necessitates further research in these areas. In this book various interesting issues related to the intelligent information models and methods as well as their advanced applications, database systems applications, data models and their analysis, and digital multimedia methods and applications are presented and discussed both from the practical and theoretical points of view. The book is organized in four parts devoted to intelligent systems models and methods, intelligent systems advanced applications, database systems methods and applications, and multimedia systems methods and applications. The book will be interesting for both practitioners and researchers, especially graduate and PhD students of information technology and computer science, as well more experienced ...

  9. 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.

  10. 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.

  11. 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

  12. Safeguards Summary Event List (SSEL)

    International Nuclear Information System (INIS)

    1984-03-01

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

  13. Safeguards Summary Event List (SSEL)

    International Nuclear Information System (INIS)

    1983-02-01

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

  14. Safeguards Summary Event List (SSEL)

    International Nuclear Information System (INIS)

    1982-07-01

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

  15. Reactor safeguards against insider sabotage

    International Nuclear Information System (INIS)

    Bennett, H.A.

    1982-03-01

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

  16. 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

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

    International Nuclear Information System (INIS)

    Reynolds, D.A.

    1981-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-07-24

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

  19. 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)

  20. 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.)

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

    International Nuclear Information System (INIS)

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

    1984-07-01

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

  2. Safeguards information handling and treatment

    International Nuclear Information System (INIS)

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

    2001-01-01

    Many states are currently discussing the new additional protocol (INFCIRC/540). This expanded framework is expected to establish the additional confirmation that there are no undeclared activities and facilities in that state. The information collected by the IAEA mainly comes from three different sources: information either provided by the state, collected by the IAEA, and from open sources. This information can be uncertain, incomplete, imprecise, not fully reliable, contradictory, etc. Hence, there is a need for a mathematical framework that provides a basis for handling and treatment of multidimensional information of varying quality. We use a linguistic assessment based on fuzzy set theory, as a flexible and realistic approach. The concept of a linguistic variable serves the purpose of providing a means of approximated characterization of information that may be imprecise, too complex or ill-defined, for which the traditional quantitative approach does not give an adequate answer. In the application of this linguistic assessment approach, a problem arises on how to aggregate linguistic information. Two different approaches can be followed: (1) approximation approach using the associated membership function; (2) symbolic approach acting by the direct computation on labels, where the use of membership function and the linguistic approximation is unnecessary, which makes computation simple and quick. To manipulate the linguistic information in this context, we work with aggregation operators for combining the linguistic non-weighted and weighted values by direct computation on labels, like the Min-type and Max-type weighted aggregation operators as well as the median aggregation operator. A case study on the application of these aggregation operators to the fusion of safeguards relevant information is given. The IAEA Physical Model of the nuclear fuel cycle can be taken as a systematic and comprehensive indicator system. It identifies and describes indicators of

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

    International Nuclear Information System (INIS)

    Olaru, Vasilica; Ivana, Tiberiu; Epure, Gheorghe

    2010-01-01

    The nuclear activity in ROMANIA was for many years under Traditional Safeguards (TS) and has developed in good conditions this type of nuclear safeguards. Now, the opportunity exists to improve the performance and quality of the safeguards activity and increase the accountancy and control of nuclear material by passing to Integrated Safeguards (IS). The legal framework is the Law 100/2000 for ratification of the Protocol between Romania and International Atomic Energy Agency (IAEA), additional to the Agreement between the Socialist Republic of Romania Government and IAEA related to safeguards as part of the Treaty on the non-proliferation of nuclear weapons published in the Official Gazette no. 3/31 January 1970, and the Additional Protocol content published in the Official Gazette no. 295/ 29.06.2000. The first discussion about Integrated Safeguards (IS) between Nuclear Fuel Plant (NFP) representatives and IAEA inspectors was in June 2005. In Feb. 2007 an IAEA mission visited NFP and established the main steps for implementing the IS. There were visited the storages, technological flow, and was reviewed the disposal times for different nuclear materials, the applied chemical analysis, measuring methods, weighting method and elaborating procedure of the documents and lists. At that time the IAEA and NFP representatives established the main points for starting the IS at NFP: performing the Short Notice Random Inspections (SNRI); communication of the days established for SNRI for each year; communication of the estimated deliveries and shipments for first quarter and then for the rest of the year: daily mail box declaration (DD) with respect to the deposit time for several nuclear materials i.e. advance notification (AN) for each nuclear material transfer (shipments and receipts), others. At 01 June 2007 Romania has passed officially to Integrated Safeguards and NFP (WRMD) has taken all measures to implement this objective. (authors)

  4. Planning of Medium- and Long-Term Strategy for the Safeguards Technology Development

    International Nuclear Information System (INIS)

    Shin, Dong Hoon; Ahn, Gil Hoon; Choi, Kwan Gyu

    2009-01-01

    In Rep. of Korea, active safeguards technology development suitable to phase of a nuclear advanced country is necessary because of below reasons. First reasons are '6th ranked position in the nuclear energy generation all over the world', 'continuously increased outcomes in the various nuclear fields such as research or patent', 'strengthened intention of the new government for nuclear industries', and 'weakness of the R and D foundation related to the safeguards technology'. Second reasons are optimization necessity of the effectiveness and efficiency of safeguards according to enlargement of the SSAC (State Systems of Accounting for and Control) role. The reason of the enlargement of the SSAC is IAEA IS (Integrated Safeguards) application for Korea. Third reasons are necessity for the systematic national development plan considering the Korea R and D level and the degree of the difficulty of technology. This is to say, there is necessity of the system construction of safeguards technology development connected to the NuTRM(Nuclear Technology Road Map), integrated national nuclear energy promotion plans because of necessity for concentration of the technology level and development abilities which are spread in the industry fields, the academic world and research fields. So, in this study, the foundation of the advanced safeguards technology is provided through determining the priority of the individual technology of National Safeguards, establishing development strategy for the middle or long term of Safeguards technology, based on domestic and foreign status

  5. Approaches to technology education and the role of advanced educational technologies: an international orientation

    NARCIS (Netherlands)

    Vries, de M.J.; Gordon, A.; Hacker, M.; Vries, de M.J.

    1993-01-01

    To be able to understand the value of integrating advanced technologies into existing technology education programmes, it is necessary to look at the features of various approaches that can be distinguished in various countries. Here eight approaches are described: the craft oriented approach, the

  6. 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)

  7. Development of Measurement Techniques For Strengthening Nuclear Safeguards

    International Nuclear Information System (INIS)

    Badawy, I.

    2007-01-01

    The strategy of nuclear safeguards is based on the accounting and control of nuclear materials, nuclear technologies and activities in a State in order to attain its ''Legal'' goals of the application of atomic energy. The present paper investigates the development in the measurement techniques used in the verification and control of NMs for the purpose of strengthening safeguards. Its focus is to review the recent nuclear measurement techniques used for the identification and verification of nuclear materials.The different levels of verification and the accuracy of these techniques are discussed. The implementation of stregthened safeguards; and nuclear materials verification and control in the world are mentioned. Also, the recently proposed measures to enhance the ability to detect undeclared nuclear materials, nuclear activities and facilities that would need advanced measurement techniques are indicated.

  8. 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.

  9. Nuclear safeguards in Brazil and Argentina: 25 years of ABACC

    Science.gov (United States)

    Kassenova, Togzhan

    2017-11-01

    As possessors of advanced nuclear technology, Brazil and Argentina bear special responsibility for helping the international community and neighbors in their region feel confident that their nuclear programs are peaceful, secure, and safe. Over the past 25 years, the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC) has played an indispensable role in strengthening such confidence by implementing nuclear safeguards in the two countries. Today, ABACC carries out safeguards inspections at a total of 76 nuclear facilities in Brazil and Argentina. This article describes how Brazil and Argentina view trends in the global nonproliferation regime and international nuclear safeguards, and explains how these trends relate to unique challenges and opportunities facing Brazil, Argentina, and ABACC.

  10. 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

  11. Predicting the carcinogenicity of chemicals with alternative approaches: recent advances.

    Science.gov (United States)

    Benigni, Romualdo

    2014-09-01

    Alternative approaches to the rodent bioassay are necessary for early identification of problematic drugs and biocides during the development process, and are the only practicable tool for assessing environmental chemicals with no or adequate safety documentation. This review informs on: i) the traditional prescreening through genotoxicity testing; ii) an integrative approach that assesses DNA-reactivity and ability to disorganize tissues; iii) new applications of omics technologies (ToxCast/Tox21 project); iv) a pragmatic approach aimed at filling data gaps by intrapolating/extrapolating from similar chemicals (read-across, category formation). The review also approaches the issue of the concerns about false-positive and false-negative results that prevents a wider acceptance and use of alternatives. The review addresses strengths and limitations of various proposals, and concludes on the need of differential approaches to the issue of false negatives and false positives. False negatives can be eliminated or reduced below the variability of the animal assay with conservative quantitative structure-activity relationships or in vitro tests; false positives can be cleared with ad hoc mechanistically based follow-ups. This framework can permit a reduction of animal testing and a better protection of human health.

  12. Advances in asthma in 2016: Designing individualized approaches to management.

    Science.gov (United States)

    Anderson, William C; Apter, Andrea J; Dutmer, Cullen M; Searing, Daniel A; Szefler, Stanley J

    2017-09-01

    In this year's Advances in Asthma review, we discuss viral infections in asthmatic patients and potential therapeutic agents, the microbiome, novel genetic associations with asthma, air quality and climate effects on asthma, exposures during development and long-term sequelae of childhood asthma, patient-centered outcomes research, and precision medicine. In addition, we discuss application of biomarkers to precision medicine and new information on asthma medications. New evidence indicates that rhinovirus-triggered asthma exacerbations become more severe as the degree of sensitization to dust mite and mouse increase. The 2 biggest drivers of asthma severity are an allergy pathway starting with allergic sensitization and an environmental tobacco smoke pathway. In addition, allergic sensitization and blood eosinophils can be used to select medications for management of early asthma in young children. These current findings, among others covered in this review, represent significant steps toward addressing rapidly advancing areas of knowledge that have implications for asthma management. Copyright © 2017 American Academy of Allergy, Asthma & Immunology. Published by Elsevier Inc. All rights reserved.

  13. Advances in Imaging Approaches to Fracture Risk Evaluation

    Science.gov (United States)

    Manhard, Mary Kate; Nyman, Jeffry S.; Does, Mark D.

    2016-01-01

    Fragility fractures are a growing problem worldwide, and current methods for diagnosing osteoporosis do not always identify individuals who require treatment to prevent a fracture and may misidentify those not a risk. Traditionally, fracture risk is assessed using dual-energy X-ray absorptiometry, which provides measurements of areal bone mineral density (BMD) at sites prone to fracture. Recent advances in imaging show promise in adding new information that could improve the prediction of fracture risk in the clinic. As reviewed herein, advances in quantitative computed tomography (QCT) predict hip and vertebral body strength; high resolution HR-peripheral QCT (HR-pQCT) and micro-magnetic resonance imaging (μMRI) assess the micro-architecture of trabecular bone; quantitative ultrasound (QUS) measures the modulus or tissue stiffness of cortical bone; and quantitative ultra-short echo time MRI methods quantify the concentrations of bound water and pore water in cortical bone, which reflect a variety of mechanical properties of bone. Each of these technologies provides unique characteristics of bone and may improve fracture risk diagnoses and reduce prevalence of fractures by helping to guide treatment decisions. PMID:27816505

  14. 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.

  15. IAEA safety standards and approach to safety of advanced reactors

    International Nuclear Information System (INIS)

    Gasparini, M.

    2004-01-01

    The paper presents an overview of the IAEA safety standards including their overall structure and purpose. A detailed presentation is devoted to the general approach to safety that is embodied in the current safety requirements for the design of nuclear power plants. A safety approach is proposed for the future. This approach can be used as reference for a safe design, for safety assessment and for the preparation of the safety requirements. The method proposes an integration of deterministic and risk informed concepts in the general frame of a generalized concept of safety goals and defence in depth. This methodology may provide a useful tool for the preparation of safety requirements for the design and operation of any kind of reactor including small and medium sized reactors with innovative safety features.(author)

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

    International Nuclear Information System (INIS)

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

    1987-01-01

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

  17. 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.

  18. 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

  19. Recent advances in rational approaches for enzyme engineering

    Directory of Open Access Journals (Sweden)

    Kerstin Steiner

    2012-09-01

    Full Text Available Enzymes are an attractive alternative in the asymmetric syntheses of chiral building blocks. To meet the requirements of industrial biotechnology and to introduce new functionalities, the enzymes need to be optimized by protein engineering. This article specifically reviews rational approaches for enzyme engineering and de novo enzyme design involving structure-based approaches developed in recent years for improvement of the enzymes’ performance, broadened substrate range, and creation of novel functionalities to obtain products with high added value for industrial applications.

  20. An approach to the management of locally advanced breast cancer ...

    African Journals Online (AJOL)

    female, aspects surrounding family planning ... surgery and is the current standard of care ... In the developed world, 7% of breast cancer patients have stage III disease at diagnosis. In ... of chemotherapy compared with adjuvant therapy.[6]. Regimens. Historically, regimens based on ... immunohistochemical approach. The.

  1. Recent advances in bioprinting techniques: approaches, applications and future prospects.

    Science.gov (United States)

    Li, Jipeng; Chen, Mingjiao; Fan, Xianqun; Zhou, Huifang

    2016-09-20

    Bioprinting technology shows potential in tissue engineering for the fabrication of scaffolds, cells, tissues and organs reproducibly and with high accuracy. Bioprinting technologies are mainly divided into three categories, inkjet-based bioprinting, pressure-assisted bioprinting and laser-assisted bioprinting, based on their underlying printing principles. These various printing technologies have their advantages and limitations. Bioprinting utilizes biomaterials, cells or cell factors as a "bioink" to fabricate prospective tissue structures. Biomaterial parameters such as biocompatibility, cell viability and the cellular microenvironment strongly influence the printed product. Various printing technologies have been investigated, and great progress has been made in printing various types of tissue, including vasculature, heart, bone, cartilage, skin and liver. This review introduces basic principles and key aspects of some frequently used printing technologies. We focus on recent advances in three-dimensional printing applications, current challenges and future directions.

  2. Defending against the Advanced Persistent Threat: An Optimal Control Approach

    Directory of Open Access Journals (Sweden)

    Pengdeng Li

    2018-01-01

    Full Text Available The new cyberattack pattern of advanced persistent threat (APT has posed a serious threat to modern society. This paper addresses the APT defense problem, that is, the problem of how to effectively defend against an APT campaign. Based on a novel APT attack-defense model, the effectiveness of an APT defense strategy is quantified. Thereby, the APT defense problem is modeled as an optimal control problem, in which an optimal control stands for a most effective APT defense strategy. The existence of an optimal control is proved, and an optimality system is derived. Consequently, an optimal control can be figured out by solving the optimality system. Some examples of the optimal control are given. Finally, the influence of some factors on the effectiveness of an optimal control is examined through computer experiments. These findings help organizations to work out policies of defending against APTs.

  3. Cooperative technology development: An approach to advancing energy technology

    International Nuclear Information System (INIS)

    Stern, T.

    1989-09-01

    Technology development requires an enormous financial investment over a long period of time. Scarce national and corporate resources, the result of highly competitive markets, decreased profit margins, wide currency fluctuations, and growing debt, often preclude continuous development of energy technology by single entities, i.e., corporations, institutions, or nations. Although the energy needs of the developed world are generally being met by existing institutions, it is becoming increasingly clear that existing capital formation and technology transfer structures have failed to aid developing nations in meeting their growing electricity needs. This paper will describe a method for meeting the electricity needs of the developing world through technology transfer and international cooperative technology development. The role of nuclear power and the advanced passive plant design will be discussed. (author)

  4. Advanced free space optics (FSO) a systems approach

    CERN Document Server

    Majumdar, Arun K

    2015-01-01

    This book provides a comprehensive, unified tutorial covering the most recent advances in the technology of free-space optics (FSO). It is an all-inclusive source of information on the fundamentals of FSO as well as up-to-date information on the state-of-the-art in technologies available today. This text is intended for graduate students, and will also be useful for research scientists and engineers with an interest in the field. FSO communication is a practical solution for creating a three dimensional global broadband communications grid, offering bandwidths far beyond what is possible in the Radio Frequency (RF) range. However, the attributes of atmospheric turbulence and scattering impose perennial limitations on availability and reliability of FSO links. From a systems point-of-view, this groundbreaking book provides a thorough understanding of channel behavior, which can be used to design and evaluate optimum transmission techniques that operate under realistic atmospheric conditions. Topics addressed...

  5. Enhanced portability of safeguards measurements tools

    International Nuclear Information System (INIS)

    Swinth, K.L.; Brackenbush, L.W.; Braby, L.A.; Eschbach, P.A.

    1994-03-01

    In recent years, computers have decreased in size from cubic meter volumes to units that can fit in the palm of the hand. At the same time, the capability of the computers has increased due to both faster electronics and improvements in software. Similar changes have occurred in other electronic devices, primarily because of the decrease in size of the electronics and the incorporation of smart electronics (microprocessors). Similar decreases in the size of the detectors used in radiation detection, however, have not yet occurred. Reduction in detector size requires advances in materials to provide higher efficiency in a smaller volume. Improved intrinsic efficiency of detectors does not always meet safeguards needs because resolution of individual photopeaks may be more important than efficiency. Recent advances at the Pacific Northwest Laboratory have led to smaller multichannel analyzers and more compact detector electronics. In related studies, the performance of the new scintillation detectors has been explored

  6. 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

  7. 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

  8. 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)

  9. A Trait-Based Approach to Advance Coral Reef Science.

    Science.gov (United States)

    Madin, Joshua S; Hoogenboom, Mia O; Connolly, Sean R; Darling, Emily S; Falster, Daniel S; Huang, Danwei; Keith, Sally A; Mizerek, Toni; Pandolfi, John M; Putnam, Hollie M; Baird, Andrew H

    2016-06-01

    Coral reefs are biologically diverse and ecologically complex ecosystems constructed by stony corals. Despite decades of research, basic coral population biology and community ecology questions remain. Quantifying trait variation among species can help resolve these questions, but progress has been hampered by a paucity of trait data for the many, often rare, species and by a reliance on nonquantitative approaches. Therefore, we propose filling data gaps by prioritizing traits that are easy to measure, estimating key traits for species with missing data, and identifying 'supertraits' that capture a large amount of variation for a range of biological and ecological processes. Such an approach can accelerate our understanding of coral ecology and our ability to protect critically threatened global ecosystems. Copyright © 2016 Elsevier Ltd. All rights reserved.

  10. New advances in the statistical parton distributions approach*

    Directory of Open Access Journals (Sweden)

    Soffer Jacques

    2016-01-01

    Full Text Available The quantum statistical parton distributions approach proposed more than one decade ago is revisited by considering a larger set of recent and accurate Deep Inelastic Scattering experimental results. It enables us to improve the description of the data by means of a new determination of the parton distributions. This global next-to-leading order QCD analysis leads to a good description of several structure functions, involving unpolarized parton distributions and helicity distributions, in terms of a rather small number of free parameters. There are many serious challenging issues. The predictions of this theoretical approach will be tested for single-jet production and charge asymmetry in W± production in p̄p and pp collisions up to LHC energies, using recent data and also for forthcoming experimental results.

  11. ADVANCED APPROACH TO PRODUCTION WORKFLOW COMPOSITION ON ENGINEERING KNOWLEDGE PORTALS

    OpenAIRE

    Novogrudska, Rina; Kot, Tatyana; Globa, Larisa; Schill, Alexander

    2016-01-01

    Background. In the environment of engineering knowledge portals great amount of partial workflows is concentrated. Such workflows are composed into general workflow aiming to perform real complex production task. Characteristics of partial workflows and general workflow structure are not studied enough, that affects the impossibility of general production workflowdynamic composition.Objective. Creating an approach to the general production workflow dynamic composition based on the partial wor...

  12. A trait-based approach to advance coral reef science

    DEFF Research Database (Denmark)

    Madin, Joshua S.; Hoogenboom, Mia O.; Connolly, Sean R.

    2016-01-01

    Coral reefs are biologically diverse and ecologically complex ecosystems constructed by stony corals. Despite decades of research, basic coral population biology and community ecology questions remain. Quantifying trait variation among species can help resolve these questions, but progress has been...... a large amount of variation for a range of biological and ecological processes. Such an approach can accelerate our understanding of coral ecology and our ability to protect critically threatened global ecosystems....

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

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  14. Probabilistic assessment of nuclear safety and safeguards

    International Nuclear Information System (INIS)

    Higson, D.J.

    1987-01-01

    Nuclear reactor accidents and diversions of materials from the nuclear fuel cycle are perceived by many people as particularly serious threats to society. Probabilistic assessment is a rational approach to the evaluation of both threats, and may provide a basis for decisions on appropriate actions to control them. Probabilistic method have become standard tools used in the analysis of safety, but there are disagreements on the criteria to be applied when assessing the results of analysis. Probabilistic analysis and assessment of the effectiveness of nuclear material safeguards are still at an early stage of development. (author)

  15. 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.

  16. 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.

  17. 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

  18. Advanced Modular Power Approach to Affordable, Supportable Space Systems

    Science.gov (United States)

    Oeftering, Richard C.; Kimnach, Greg L.; Fincannon, James; Mckissock,, Barbara I.; Loyselle, Patricia L.; Wong, Edmond

    2013-01-01

    Recent studies of missions to the Moon, Mars and Near Earth Asteroids (NEA) indicate that these missions often involve several distinct separately launched vehicles that must ultimately be integrated together in-flight and operate as one unit. Therefore, it is important to see these vehicles as elements of a larger segmented spacecraft rather than separate spacecraft flying in formation. The evolution of large multi-vehicle exploration architecture creates the need (and opportunity) to establish a global power architecture that is common across all vehicles. The Advanced Exploration Systems (AES) Modular Power System (AMPS) project managed by NASA Glenn Research Center (GRC) is aimed at establishing the modular power system architecture that will enable power systems to be built from a common set of modular building blocks. The project is developing, demonstrating and evaluating key modular power technologies that are expected to minimize non-recurring development costs, reduce recurring integration costs, as well as, mission operational and support costs. Further, modular power is expected to enhance mission flexibility, vehicle reliability, scalability and overall mission supportability. The AMPS project not only supports multi-vehicle architectures but should enable multi-mission capability as well. The AMPS technology development involves near term demonstrations involving developmental prototype vehicles and field demonstrations. These operational demonstrations not only serve as a means of evaluating modular technology but also provide feedback to developers that assure that they progress toward truly flexible and operationally supportable modular power architecture.

  19. Engaging Patients With Advance Directives Using an Information Visualization Approach.

    Science.gov (United States)

    Woollen, Janet; Bakken, Suzanne

    2016-01-01

    Despite the benefits of advance directives (AD) to patients and care providers, they are often not completed due to lack of patient awareness. The purpose of the current article is to advocate for creation and use of an innovative information visualization (infovisual) as a health communication tool aimed at improving AD dissemination and engagement. The infovisual would promote AD awareness by encouraging patients to learn about their options and inspire contemplation and conversation regarding their end-of-life (EOL) journey. An infovisual may be able to communicate insights that are often communicated in words, but are much more powerfully communicated by example. Furthermore, an infovisual could facilitate vivid understanding of options and inspire the beginning of often difficult conversations among care providers, patients, and loved ones. It may also save clinicians time, as care providers may be able to spend less time explaining details of EOL care options. Use of an infovisual could assist in ensuring a well-planned EOL journey. Copyright 2016, SLACK Incorporated.

  20. Advances in a Distributed Approach for Ocean Model Data Interoperability

    Directory of Open Access Journals (Sweden)

    Richard P. Signell

    2014-03-01

    Full Text Available An infrastructure for earth science data is emerging across the globe based on common data models and web services. As we evolve from custom file formats and web sites to standards-based web services and tools, data is becoming easier to distribute, find and retrieve, leaving more time for science. We describe recent advances that make it easier for ocean model providers to share their data, and for users to search, access, analyze and visualize ocean data using MATLAB® and Python®. These include a technique for modelers to create aggregated, Climate and Forecast (CF metadata convention datasets from collections of non-standard Network Common Data Form (NetCDF output files, the capability to remotely access data from CF-1.6-compliant NetCDF files using the Open Geospatial Consortium (OGC Sensor Observation Service (SOS, a metadata standard for unstructured grid model output (UGRID, and tools that utilize both CF and UGRID standards to allow interoperable data search, browse and access. We use examples from the U.S. Integrated Ocean Observing System (IOOS® Coastal and Ocean Modeling Testbed, a project in which modelers using both structured and unstructured grid model output needed to share their results, to compare their results with other models, and to compare models with observed data. The same techniques used here for ocean modeling output can be applied to atmospheric and climate model output, remote sensing data, digital terrain and bathymetric data.

  1. Advances in a distributed approach for ocean model data interoperability

    Science.gov (United States)

    Signell, Richard P.; Snowden, Derrick P.

    2014-01-01

    An infrastructure for earth science data is emerging across the globe based on common data models and web services. As we evolve from custom file formats and web sites to standards-based web services and tools, data is becoming easier to distribute, find and retrieve, leaving more time for science. We describe recent advances that make it easier for ocean model providers to share their data, and for users to search, access, analyze and visualize ocean data using MATLAB® and Python®. These include a technique for modelers to create aggregated, Climate and Forecast (CF) metadata convention datasets from collections of non-standard Network Common Data Form (NetCDF) output files, the capability to remotely access data from CF-1.6-compliant NetCDF files using the Open Geospatial Consortium (OGC) Sensor Observation Service (SOS), a metadata standard for unstructured grid model output (UGRID), and tools that utilize both CF and UGRID standards to allow interoperable data search, browse and access. We use examples from the U.S. Integrated Ocean Observing System (IOOS®) Coastal and Ocean Modeling Testbed, a project in which modelers using both structured and unstructured grid model output needed to share their results, to compare their results with other models, and to compare models with observed data. The same techniques used here for ocean modeling output can be applied to atmospheric and climate model output, remote sensing data, digital terrain and bathymetric data.

  2. SI:FatiguePro 4 Advanced Approach for Fatigue Monitoring

    International Nuclear Information System (INIS)

    Evon, Keith; Gilman, Tim; Carney, Curt

    2012-01-01

    Many nuclear plants are making commitments to implement fatigue monitoring systems in support of license renewal. Current fatigue monitoring systems use the methodology of ASME Code Subarticle NB-3200, which is a design code intended to compute a bounding cumulative usage factor (CUF). The first generation of fatigue monitoring software utilized a simplified, single stress term assumption and classical stress cycle-counting methods that take order into account such as Rainflow or Ordered Overall Range counting. Recently, the NRC has indicated in Regulatory Issue Summary 2008-30 that any fatigue analyses in support of License Renewal should use ASME Code Section III methodologies considering all six stress components. In addition, fatigue calculations for the license renewal term are required to consider the effects of environment. The implementation of a six stress term NB-3200 fatigue calculation to a Boiling Water Reactor (BWR) feedwater nozzle, including environmental effects, is the topic of this paper. Differences in results between the advanced methodology and the simplified methodology are discussed. (author)

  3. Policy and technical issues for international safeguards in nuclear weapons states

    International Nuclear Information System (INIS)

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

    1994-01-01

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

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

    International Nuclear Information System (INIS)

    Synetos, Sotiris

    2013-01-01

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

  5. Data analysis of asymmetric structures advanced approaches in computational statistics

    CERN Document Server

    Saito, Takayuki

    2004-01-01

    Data Analysis of Asymmetric Structures provides a comprehensive presentation of a variety of models and theories for the analysis of asymmetry and its applications and provides a wealth of new approaches in every section. It meets both the practical and theoretical needs of research professionals across a wide range of disciplines and  considers data analysis in fields such as psychology, sociology, social science, ecology, and marketing. In seven comprehensive chapters this guide details theories, methods, and models for the analysis of asymmetric structures in a variety of disciplines and presents future opportunities and challenges affecting research developments and business applications.

  6. Advances in Assays and Analytical Approaches for Botulinum Toxin Detection

    Energy Technology Data Exchange (ETDEWEB)

    Grate, Jay W.; Ozanich, Richard M.; Warner, Marvin G.; Bruckner-Lea, Cindy J.; Marks, James D.

    2010-08-04

    Methods to detect botulinum toxin, the most poisonous substance known, are reviewed. Current assays are being developed with two main objectives in mind: 1) to obtain sufficiently low detection limits to replace the mouse bioassay with an in vitro assay, and 2) to develop rapid assays for screening purposes that are as sensitive as possible while requiring an hour or less to process the sample an obtain the result. This review emphasizes the diverse analytical approaches and devices that have been developed over the last decade, while also briefly reviewing representative older immunoassays to provide background and context.

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

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  8. Advances in biohydrogen production processes: An approach towards commercialization

    Energy Technology Data Exchange (ETDEWEB)

    Das, Debabrata [Department of Biotechnology, Indian Institute of Technology, Kharagpur 721302, West Bengal (India)

    2009-09-15

    Biological H{sub 2} production has an edge over its chemical counterpart mainly because it is environmentally benign. Despite having simpler technology, higher evolution rate of H{sub 2} and the wide spectrum of substrate utilization, the major deterrent of anaerobic dark fermentation process stems from its lower achievable yields. Theoretically, the maximum H{sub 2} yield is 4 mol H{sub 2}/mol glucose when glucose is completely metabolized to acetate or acetone in the anaerobic process. But it is somewhat difficult to achieve the complete degradation of glucose to carbon dioxide and H{sub 2} through anaerobic dark fermentation. Moreover, this yield appears too low to be economically viable as an alternative to the existing chemical or electrochemical processes of hydrogen generation. Intensive research studies have already been carried out on the advancement of these processes, such as the development of genetically modified microorganism, improvement of the reactor designs, use of different solid matrices for the immobilization of whole cells, development of two-stage processes, and higher H{sub 2} production rates. Maximum H{sub 2} yield is found to be 5.1 mol H{sub 2}/mol glucose. However, major bottlenecks for the commercialization of these processes are lower H{sub 2} yield and rate of H{sub 2} production. Competent microbial cultures are required to handle waste materials efficiently, which are usually complex in nature. This will serve dual purposes: clean energy generation and bioremediation. Scale-up studies on fermentative H{sub 2} production processes have been done successfully. Pilot plant trials of the photo-fermentation processes require more attention. Use of cheaper raw materials and efficient biological H{sub 2} production processes will surely make them more competitive with the conventional H{sub 2} generation processes in near future. (author)

  9. Advanced methods in NDE using machine learning approaches

    Science.gov (United States)

    Wunderlich, Christian; Tschöpe, Constanze; Duckhorn, Frank

    2018-04-01

    Machine learning (ML) methods and algorithms have been applied recently with great success in quality control and predictive maintenance. Its goal to build new and/or leverage existing algorithms to learn from training data and give accurate predictions, or to find patterns, particularly with new and unseen similar data, fits perfectly to Non-Destructive Evaluation. The advantages of ML in NDE are obvious in such tasks as pattern recognition in acoustic signals or automated processing of images from X-ray, Ultrasonics or optical methods. Fraunhofer IKTS is using machine learning algorithms in acoustic signal analysis. The approach