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Sample records for nuclear material measurements

  1. Measurement control program for nuclear material accounting

    International Nuclear Information System (INIS)

    Brouns, R.J.; Roberts, F.P.; Merrill, J.A.; Brown, W.B.

    1980-06-01

    A measurement control program for nuclear material accounting monitors and controls the quality of the measurments of special nuclear material that are involved in material balances. The quality is monitored by collecting data from which the current precision and accuracy of measurements can be evaluated. The quality is controlled by evaluations, reviews, and other administrative measures for control of selection or design of facilities, equipment and measurement methods and the training and qualification of personnel who perform SNM measurements. This report describes the most important elements of a program by which management can monitor and control measurement quality

  2. Considerations for sampling nuclear materials for SNM accounting measurements. Special nuclear material accountability report

    International Nuclear Information System (INIS)

    Brouns, R.J.; Roberts, F.P.; Upson, U.L.

    1978-05-01

    This report presents principles and guidelines for sampling nuclear materials to measure chemical and isotopic content of the material. Development of sampling plans and procedures that maintain the random and systematic errors of sampling within acceptable limits for SNM(Special Nuclear Materials) accounting purposes are emphasized

  3. Nuclear material measurement system in Brazil

    International Nuclear Information System (INIS)

    Almeida, S.G. de.

    1988-01-01

    The description of the activities developed at the Safeguards Laboratory of Brazilian Nuclear Energy Commission is done. The methods and techniques used for measuring and evaluating nuclear materials and facilities are presented. (E.G.) [pt

  4. Topical understandings of nuclear material measurement · accountancy and quality assurance

    International Nuclear Information System (INIS)

    Kikuchi, Masahiro; Muraoka, Susumu; Osabe, Takeshi; Terada, Hiromi; Shimizu, Kenichi; Ohtani, Tetsuo; Fujimaki, Kazunori; Ishikawa, Tadatsugu; Shinohara, Yoshinori

    2002-01-01

    Nuclear material measurement is an important measure to determine the amount of nuclear material of each stage such as receipt, shipment, inventory and hold-up. The material accountancy based on the material balance among the measurements is a measure to control of nuclear material. The material accountancy, from the technical aspect, can be used as promising measures for purposes from operator's level to state's level such as the nuclear safety, property control and environmental preservation other than safeguards measures only to conclude no diversion of nuclear material. This paper discusses various purposes of nuclear material measurements and clarifies the certain function such as quality assurance to be expected at each purpose. Based on the discussion, critical points for the quality assurance of each stage are studied. (author)

  5. The use of measurement uncertainty in nuclear materials accuracy and verification

    International Nuclear Information System (INIS)

    Alique, O.; Vaccaro, S.; Svedkauskaite, J.

    2015-01-01

    EURATOM nuclear safeguards are based on the nuclear operators’ accounting for and declaring of the amounts of nuclear materials in their possession, as well as on the European Commission verifying the correctness and completeness of such declarations by means of conformity assessment practices. Both the accountancy and the verification processes comprise the measurements of amounts and characteristics of nuclear materials. The uncertainties associated to these measurements play an important role in the reliability of the results of nuclear material accountancy and verification. The document “JCGM 100:2008 Evaluation of measurement data – Guide to the expression of uncertainty in measurement” - issued jointly by the International Bureau of Weights and Measures (BIPM) and international organisations for metrology, standardisation and accreditation in chemistry, physics and electro technology - describes a universal, internally consistent, transparent and applicable method for the evaluation and expression of uncertainty in measurements. This paper discusses different processes of nuclear materials accountancy and verification where measurement uncertainty plays a significant role. It also suggests the way measurement uncertainty could be used to enhance the reliability of the results of the nuclear materials accountancy and verification processes.

  6. Nuclear measurements and reference materials

    International Nuclear Information System (INIS)

    1988-01-01

    This report summarizes the progress of the JRC programs on nuclear data, nuclear metrology, nuclear reference materials and non-nuclear reference materials. Budget restrictions and personnel difficulties were encountered during 1987. Fission properties of 235 U as a function of neutron energy and of the resonances can be successfully described on the basis of a three exit channel fission model. Double differential neutron emission cross-sections were accomplished on 7 Li and were started for the tritium production cross-section of 9 Be. Reference materials of uranium minerals and ores were prepared. Special nuclear targets were prepared. A batch of 250 g of Pu0 2 was characterized in view of certification as reference material for the elemental assay of plutonium

  7. REVIEW OF EQUIPMENT USED IN RUSSIAN PRACTICE FOR ACCOUNTING MEASUREMENTS OF NUCLEAR MATERIALS

    International Nuclear Information System (INIS)

    NEYMOTIN, L.

    1999-01-01

    The objective of this work was to analyze instrumentation and methodologies used at Russian nuclear facilities for measurement of item nuclear materials, materials in bulk form, and waste streams; specify possibilities for the application of accounting measurements; and develop recommendations for improvement. The major steps and results: Representative conversion, enrichment (gas centrifuge), fuel fabrication, spent fuel reprocessing, and chemical-metallurgical production facilities in Russia were selected; Full lists of nuclear materials were prepared; Information about measurement methods and instrumentation for each type of nuclear material were gathered; and Recommendations on methodological and instrumentation support of accounting measurements for all types of materials were formulated. The analysis showed that the existing measurement methods and instrumentation serve mostly to support the technological process control and nuclear and radiation safety control. Requirements for these applications are lower than requirements for MC and A applications. To improve the state of MC and A at Russian nuclear facilities, significant changes in instrumentation support will be required, specifically in weighing equipment, volume measurements, and destructive and non-destructive analysis equipment, along with certified reference materials

  8. Measures Against-Illicit Trafficking of Nuclear Materials and Other Radioactive Sources

    International Nuclear Information System (INIS)

    Barakat, M.B.; Nassef, M.H.; El Mongy, S.A.

    2008-01-01

    Since the early nineties, illicit trafficking (IT) of nuclear materials and radioactive sources appeared as a new trend which raised the concern of the international community due to the grave consequences that would merge if these materials or radioactive sources fell into the hands of terrorist groups. However, by the end of the last century illicit trafficking of nuclear materials and radioactive sources lost its considerable salience, in spite of seizure of considerable amounts of 2 '3'5U (76% enrichment) in Bulgaria (May 1999) and also 235 U (30% enrichment) in Georgia (April 2000). Nevertheless, IT should be always considered as a continued and viable threat to the international community. Awareness of the problem should be developed and maintained among concerned circles as the first step towards combating illicit trafficking of nuclear materials and radioactive sources. Illicit trafficking of nuclear and radioactive materials needs serious consideration and proper attention by the governmental law enforcement authorities. Measures to combat with IT of nuclear material or radioactive sources should be effective in recovery, of stolen, removed or lost nuclear materials or radioactive sources due to the failure of the physical protection system or the State System Accounting and Control (SSAC) system which are normally applied for protecting these materials against illegal actions. Measures such as use of modern and efficient radiation monitoring equipment at the borders inspection points, is an important step in preventing the illicit trafficking of nuclear and radioactive materials across the borders. Also providing radiological training to specific personnel and workers in this field will minimize the consequences of a radiological attack in case of its occurrence. There is a real need to start to enter into cooperative agreements to strengthen borders security under the umbrella of IAEA to faster as an international cooperation in the illicit trafficking

  9. Considerations for sampling nuclear materials for SNM accounting measurements

    International Nuclear Information System (INIS)

    Brouns, R.J.; Roberts, F.P.; Upson, U.L.

    1978-01-01

    This report presents principles and guidelines for sampling nuclear materials to measure chemical and isotopic content of the material. Development of sampling plans and procedures that maintain the random and systematic errors of sampling within acceptable limits for SNM accounting purposes are emphasized

  10. 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

  11. Notification determining technical details concerning measures for transportation of nuclear fuel materials

    International Nuclear Information System (INIS)

    1977-01-01

    These provisions are established on the basis of and to enforce ''The regulation for installation and operation of reactor'', ''The regulation concerning the fabricating business of nuclear fuel'' and ''The regulations concerning the reprocessing business of spent fuel''. The terms used hereinafter are according to those used in such regulations. The limit of radioactivity concentration of things contaminated by the nuclear fuel materials which are not required to be enclosed in vessels is defined in the lists attached. In the applications for the approval of the measures concerning the transport of things remarkably difficult to be enclosed in vessels, the name and the address of the applicant, the kind, quantity, form and constitution of the thing contaminated by the nuclear fuel materials to be transported, the date and route of the transport and the measures for the prevention of injuries during the transport must be written. The limit of quantity of nuclear fuel materials classifying the performance of vessels is defined respectively in the lists attached. The radiation dose rates provided for by the Director General of the Science and Technology Agency concerning transported things and transporting apparatuses are 200 millirem per hour on the surfaces of such things and containers. The nuclear fission materials specified, for which the measures for the prevention of criticality are especially required, include uranium 233, uranium 235, plutonium 238, plutonium 239, plutonium 241, and the chemical compounds of such substances, and the nuclear fuel materials containing one or two and more of such substances, excluding the nuclear fuel materials with less than 15 grams of such uranium and plutonium. (Okada, K.)

  12. Characterization of Nuclear Materials Using Complex of Non-Destructive and Mass-Spectroscopy Methods of Measurements

    International Nuclear Information System (INIS)

    Gorbunova, A.; Kramchaninov, A.

    2015-01-01

    Information and Analytical Centre for nuclear materials investigations was established in Russian Federation in the February 2 of 2009 by ROSATOM State Atomic Energy Corporation (the order #80). Its purpose is in preventing unauthorized access to nuclear materials and excluding their illicit traffic. Information and Analytical Centre includes analytical laboratory to provide composition and properties of nuclear materials of unknown origin for their identification. According to Regulation the Centre deals with: · identification of nuclear materials of unknown origin to provide information about their composition and properties; · arbitration analyzes of nuclear materials; · comprehensive research of nuclear and radioactive materials for developing techniques characterization of materials; · interlaboratory measurements; · measurements for control and accounting; · confirmatory measurements. Complex of non-destructive and mass-spectroscopy techniques was developed for the measurements. The complex consists of: · gamma-ray techniques on the base of MGAU, MGA and FRAM codes for uranium and plutonium isotopic composition; · gravimetrical technique with gamma-spectroscopy in addition for uranium content; · calorimetric technique for plutonium mass; · neutron multiplicity technique for plutonium mass; · measurement technique on the base of mass-spectroscopy for uranium isotopic composition; · measurement technique on the base of mass-spectroscopy for metallic impurities. Complex satisfies the state regulation requirements of ensuring the uniformity of measurements including the Russian Federation Federal Law on Ensuring the Uniformity of Measurements #102-FZ, Interstate Standard GOST R ISO/IEC 17025-2006, National Standards of Russian Federation GOST R 8.563-2009, GOST R 8.703-2010, Federal Regulations NRB-99/2009, OSPORB 99/2010. Created complex is provided in reference materials, equipment end certificated techniques. The complex is included in accredited

  13. Nuclear Security Systems and Measures for the Detection of Nuclear and Other Radioactive Material out of Regulatory Control. Implementing Guide

    International Nuclear Information System (INIS)

    2013-01-01

    Nuclear terrorism and the illicit trafficking of nuclear and other radioactive material threaten the security of all States. There are large quantities of diverse radioactive material in existence, which are used in areas such as health, the environment, agriculture and industry. The possibility that nuclear and other radioactive material may be used for terrorist acts cannot be ruled out in the current global situation. States have responded to this risk by engaging in a collective commitment to strengthen the protection and control of such material, and to establish capabilities for detection and response to nuclear and other radioactive material out of regulatory control. Through its nuclear security programme, the IAEA supports States to establish, maintain and sustain an effective nuclear security regime. The IAEA has adopted a comprehensive approach to nuclear security. This approach recognizes that an effective national nuclear security regime builds on: the implementation of relevant international legal instruments; information protection; physical protection; material accounting and control; detection of and response to trafficking in nuclear and other radioactive material; national response plans; and contingency measures. Within its nuclear security programme, the IAEA aims to assist States in implementing and sustaining such a regime in a coherent and integrated manner. Each State carries the full responsibility for nuclear security, specifically: to provide for the security of nuclear and other radioactive material and associated facilities and activities; to ensure the security of such material in use, storage or in transport; to combat illicit trafficking; and to detect and respond to nuclear security events. This is an Implementing Guide on nuclear security systems and measures for the detection of nuclear and other radioactive material out of regulatory control. The objective of the publication is to provide guidance to Member States for the

  14. The regulations concerning refining business of nuclear source material and nuclear fuel materials

    International Nuclear Information System (INIS)

    1987-01-01

    Regulations specified here cover application for designation of undertakings of refining (spallation and eaching filtration facilities, thickening facilities, refining facilities, nuclear material substances or nuclear fuel substances storage facilities, waste disposal facilities, etc.), application for permission for alteration (business management plan, procurement plan, fund raising plan, etc.), application for approval of merger (procedure, conditions, reason and date of merger, etc.), submission of report on alteration (location, structure, arrangements processes and construction plan for refining facilities, etc.), revocation of designation, rules for records, rules for safety (personnel, organization, safety training for employees, handling of important apparatus and tools, monitoring and removal of comtaminants, management of radioactivity measuring devices, inspection and testing, acceptance, transport and storage of nuclear material and fuel, etc.), measures for emergency, submission of report on abolition of an undertaking, submission of report on disorganization, measures required in the wake of revocation of designation, submission of information report (exposure to radioactive rays, stolen or missing nuclear material or nuclear fuel, unusual leak of nuclear fuel or material contaminated with nuclear fuel), etc. (Nogami, K.)

  15. THE NUCLEAR MATERIAL MEASUREMENT PROGRAM PLAN FOR GOSATOMNADZOR OF RUSSIA

    International Nuclear Information System (INIS)

    Bokov, Dmitry; Byers, Kenneth R.

    2003-01-01

    As the Russian State regulatory agency responsible for oversight of nuclear material control and accounting (MC and A), Gosatomnadzor of Russia determines the status of the MC and A programs at Russian facilites by testing the nuclear material inventory for accounting record accuracy. Currently, Gosatomnadzor is developing and implementing an approach to planning and conducting MC and A inspections using non-destructive assay (NDA) instruments that will provide for consistent application of MC and A measurement inspection objectives throughtout Russia. This Gosatomnadzor NDA Program Plan documents current NDA measurement capability in all regions of Gosatomnadzor; provides justification for upgrades to equipment, procedures and training; and defines the inspector-facility operator interface as it relates to NDA measurement equipment use. This plan covers a three-year measurement program cycle, but will be reviewed and updated annually to ensure that adequate inspection resources are available to meet the demands of the inspection schedule. This paper presents the elements of this plan and describes the process by which Gosatomnadzor ensures that its NDA instruments are effectively utilized, procedures are developed and certified, and inspection personnel are properly trained to provide assurance that Russian nuclear facilities are in compliance with Russian MC and A regulations.

  16. Measures against illicit trafficking of nuclear and other radioactive materials in the Slovak Republic

    International Nuclear Information System (INIS)

    Bezak, S.

    2001-01-01

    Full text: This presentation contains description of measures used in the Slovak Republic to combat illicit trafficking of nuclear and other radioactive materials. The main goal of these measures is to allow safe and effective utilization of nuclear and other radioactive materials under surveillance of responsible state authorities as well as recover materials that were removed form legal utilization despite the preventive measures. Prevention is the most effective and the cheapest way how to overcome problems. An important precondition for prevention is existence of a national (or state) system for controlled utilization of nuclear and other radioactive materials completed by an effective physical protection of these materials and facilities involved and supported by sufficient low enforcement. A state system of accounting for and control of nuclear materials in Slovakia is based on the IAEA INFCIRC/153 requirements. A fact that the IAEA inspectors never have recognized any unaccounted nuclear material could be the best proof of its quality. Physical protection system in both Slovak NPPs is based on principles applied in development of advanced physical protection systems used in western NPPs. Technological systems and nuclear materials are categorized into three categories - first one is most sensitive. Barriers of each category zone are equipped with sufficient detection systems and are monitored by TV system. The system is operated by NPPs operators. Entrances are guarded by private security guards. Response forces are created by the police. A legal support provides the Act No. 130/1998 on peaceful use of nuclear energy and regulations on accounting and control of nuclear materials, on physical protection of nuclear facilities and nuclear materials and on transports of nuclear materials and radioactive wastes. The Criminal Code of the Slovak Republic has been amended and an illegal possession of nuclear and radioactive materials is treated as a crime. Response

  17. Total gamma activity measurements for determining the radioactivity of residual materials from nuclear power stations

    International Nuclear Information System (INIS)

    Auler, I.; Meyer, M.; Stickelmann, J.

    1995-01-01

    Large amounts of residual materials from retrofitting measures and from decommissioning of nuclear power stations shows such a weak level of radioactivity that they could be released after decision measurements. Expenses incurred with complex geometry cannot be taken with common methods. NIS developed a Release Measurement Facility (RMF) based on total gamma activity measurements especially for these kind of residual materials. The RMF has been applied for decision measurements in different nuclear power plants. Altogether about 2,000 Mg of various types of materials have been measured up to now. More than 90 % of these materials could be released 0 without any restriction after decision measurements

  18. International target values 2000 for measurement uncertainties in safeguarding nuclear materials

    International Nuclear Information System (INIS)

    Aigner, H.; Binner, R.; Kuhn, E.

    2001-01-01

    The IAEA has prepared a revised and updated version of International Target Values (ITVs) for uncertainty components in measurements of nuclear material. The ITVs represent uncertainties to be considered in judging the reliability of analytical techniques applied to industrial nuclear and fissile material subject to safeguards verification. The tabulated values represent estimates of the 'state of the practice' which ought to be achievable under routine conditions by adequately equipped, experienced laboratories. The ITVs 2000 are intended to be used by plant operators and safeguards organizations as a reference of the quality of measurements achievable in nuclear material accountancy, and for planning purposes. The IAEA prepared a draft of a technical report presenting the proposed ITVs 2000, and in April 2000 the chairmen or officers of the panels or organizations listed below were invited to co- author the report and to submit the draft to a discussion by their panels and organizations. Euratom Safeguards Inspectorate, ESAKDA Working Group on Destructive Analysis, ESARDA Working Group on Non Destructive Analysis, Institute of Nuclear Material Management, Japanese Expert Group on ITV-2000, ISO Working Group on Analyses in Spent Fuel Reprocessing, ISO Working Group on Analyses in Uranium Fuel Fabrication, ISO Working Group on Analyses in MOX Fuel Fabrication, Agencia Brasileno-Argentina de Contabilidad y Control de Materiales Nucleares (ABACC). Comments from the above groups were received and incorporated into the final version of the document, completed in April 2001. The ITVs 2000 represent target standard uncertainties, expressing the precision achievable under stipulated conditions. These conditions typically fall in one of the two following categories: 'repeatability conditions' normally encountered during the measurements done within one inspection period; or 'reproducibility conditions' involving additional sources of measurement variability such as

  19. Non-Proliferation, the IAEA Safeguards System, and the importance of nuclear material measurements

    Energy Technology Data Exchange (ETDEWEB)

    Stevens, Rebecca S. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-09-18

    The objective of this project is to explain the contribution of nuclear material measurements to the system of international verification of State declarations and the non-proliferation of nuclear weapons.

  20. Time-correlated pulse-height measurements of low-multiplying nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Miller, E.C., E-mail: ericcm@umich.edu [Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, MI (United States); Dolan, J.L.; Clarke, S.D.; Pozzi, S.A. [Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, MI (United States); Tomanin, A.; Peerani, P. [European Commission EC-JRC-IPSC, Ispra (Italy); Marleau, P. [Sandia National Laboratories, Livermore, CA (United States); Mattingly, J.K. [North Carolina State University, Raleigh, NC (United States)

    2013-11-21

    Methods for the determination of the subcritical neutron multiplication of nuclear materials are of interest in the field of nuclear nonproliferation and safeguards. A series of measurements were performed at the Joint Research Center facility in Ispra, Italy to investigate the possibility of using a time-correlated pulse-height (TCPH) analysis to estimate the sub-critical multiplication of nuclear material. The objective of the measurements was to evaluate the effectiveness of this technique, and to benchmark the simulation capabilities of MCNPX-PoliMi/MPPost. In this campaign, two low-multiplication samples were measured: a 1-kg mixed oxide (MOX) powder sample and several low-mass plutonium–gallium (PuGa) disks. The measured results demonstrated that the sensitivity of the TCPH technique could not clearly distinguish samples with very-low levels of multiplication. However, the simulated TCPH distributions agree well with the measured data, within 12% for all cases, validating the simulation capabilities of MCNPX-PoliMi/MPPost. To investigate the potential of the TCPH method for identifying high-multiplication samples, the validated MCNPX-PoliMi/MPPost codes were used to simulate sources of higher multiplications. Lastly, a characterization metric, the cumulative region integral (CRI), was introduced to estimate the level of multiplication in a source. However, this response was shown to be insensitive over the range of multiplications of interest. -- Highlights: •Present results of measurements of MOX fuel and PuGa disks. •Compared measurement results to simulations performed using MCNPX-Polimi and MPPost. •Investigated using correlated γ–n pairs to determine the multiplication of a system.

  1. Technology development for nuclear material measurement and accountability

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Jong Sook; Lee, Byung Doo; Cha, Hong Ryul; Lee, Yong Duk; Choi, Hyung Nae; Nah, Won Woo; Park, Hoh Joon; Lee, Yung Kil [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-12-01

    The measurement techniques for Pu samples and spent fuel assembly were developed in support of the implementation of national inspection responsibility under the Atomic Energy Act promulgated in 1994 and a computer program was also developed to assess the total nuclear material balance by facility declared records. The results of plutonium isotopic determination by gamma-ray spectrometry with high resolution germanium detector with peak analysis codes (FRAM and MGA codes) were approached to within 1% {approx} 2% of error from chemical analysis values by mass spectrometry. A gamma-ray measurement system for underwater spent nuclear fuels was developed and tested successfully. The falsification of facility and state records can be traced with the help of the developed computer code against declared reports submitted by the concerned state. This activity eventually resulted in finding the discrepancy of accountability records. 18 figs, 20 tabs, 27 refs. (Author).

  2. Technology development for nuclear material measurement and accountability

    International Nuclear Information System (INIS)

    Hong, Jong Sook; Lee, Byung Doo; Cha, Hong Ryul; Lee, Yong Duk; Choi, Hyung Nae; Nah, Won Woo; Park, Hoh Joon; Lee, Yung Kil

    1994-12-01

    The measurement techniques for Pu samples and spent fuel assembly were developed in support of the implementation of national inspection responsibility under the Atomic Energy Act promulgated in 1994 and a computer program was also developed to assess the total nuclear material balance by facility declared records. The results of plutonium isotopic determination by gamma-ray spectrometry with high resolution germanium detector with peak analysis codes (FRAM and MGA codes) were approached to within 1% ∼ 2% of error from chemical analysis values by mass spectrometry. A gamma-ray measurement system for underwater spent nuclear fuels was developed and tested successfully. The falsification of facility and state records can be traced with the help of the developed computer code against declared reports submitted by the concerned state. This activity eventually resulted in finding the discrepancy of accountability records. 18 figs, 20 tabs, 27 refs. (Author)

  3. Progress in Gamma Ray Measurement Information Barriers for Nuclear Material Transparency Monitoring

    International Nuclear Information System (INIS)

    Wolford, J.K.; White, G.K.

    2000-01-01

    Negotiations between technical representatives of the US and the Russian Federation in support of several pending nuclear arms and nuclear material control agreements must take account of the need for assurances against the release of sensitive information. Most of these agreements involve storing nuclear material and in some cases nuclear components from stockpile weapons in specially designed containers. Strategies for monitoring the agreements typically include measuring neutron and gamma radiation from the controlled items to verify declared attributes of plutonium or highly enriched uranium. If accurate enough to be useful, these measurements will contain information about the design of the component being monitored, information considered sensitive by one or both parties to the agreement. Safeguards have evolved to prevent disclosure of this information during inspections. These measures combine hardware, software, and procedural measures to contain the sensitive data, presenting only the results needed for verification. Custom features preserve data security and guard against disclosure in case of failure. This paper summarizes the general problem and discusses currently developing solutions for a high resolution gamma ray detection system. It argues for the simplest possible implementation of several key system components

  4. Risk Informed Approach for Nuclear Security Measures for Nuclear and Other Radioactive Material out of Regulatory Control. Implementing Guide

    International Nuclear Information System (INIS)

    2015-01-01

    This publication provides guidance to States for developing a risk informed approach and for conducting threat and risk assessments as the basis for the design and implementation of sustainable nuclear security systems and measures for prevention of, detection of, and response to criminal and intentional unauthorised acts involving nuclear and other radioactive material out of regulatory control. It describes concepts and methodologies for a risk informed approach, including identification and assessment of threats, targets, and potential consequences; threat and risk assessment methodologies, and the use of risk informed approaches as the basis for informing the development and implementation of nuclear security systems and measures. The publication is an Implementing Guide within the IAEA Nuclear Security Series and is intended for use by national policy makers, law enforcement agencies and experts from competent authorities and other relevant organizations involved in the establishment, implementation, maintenance or sustainability of nuclear security systems and measures related to nuclear and other radioactive material out of regulatory control

  5. Development of measures to deal with illicit trafficking of nuclear materials in Ghana

    International Nuclear Information System (INIS)

    Schandorf, C.; Amoako, J.K.; Asiamah, S.D.

    2001-01-01

    Full text: The world has now become a global village as such no country can isolate itself from global trends. Reported cases of illicit trafficking in nuclear materials have focused international attention on ways to combat an emerging phenomenon of the 1990's. Of the 324 confirmed cases of illicit trafficking nearly 130 involved individuals trying to illegally sell radioactive materials used in medicine or industry whose unauthorized use or movement poses a danger to public health. Some other cases have involved samples of weapons-grade materials confiscated from individuals. These incidents have raised public and governmental concerns. This has prompted stronger efforts to prevent illicit nuclear trafficking by state authorities, including collaboration and co-operation with international organizational such as the IAEA. The IAEA has established the Illicit Trafficking Database Programme and is encouraging all Member States to participate and to report all incidents of illicit trafficking in nuclear materials and other radioactive materials and other radioactive sources that come to their notice. From the data available from the Regulatory Authority Information System (RAIS), Ghana, there are 344 highly enriched uranium fuel elements (998.2g) in use in the 30kW Research Reactor, (GHARR-1) and 80 radioactive materials in use in medicine, history, research and teaching. The reactor has been subjected to safeguards inspections by IAEA on regular basis. Additionally there have been on the average about nine authorized imports of radioactive into the country in the past seven years. Unlawful use of nuclear materials, through criminal or terrorist activities, may pose a proliferation treat, while unlawful use of radiation poses risks to the public. Ghana has therefore decided to established an effective counter measure against illicit trafficking in nuclear and other materials which might pose both proliferation threat as well as radiological risk to the public and

  6. Nuclear materials control and accountability criteria for upgrades measures

    International Nuclear Information System (INIS)

    Erkkila, B.H.; Hatcher, C.R.

    1998-01-01

    As a result of major political and societal changes in the past several years, methods of nuclear material control may no longer be as effective as in the past in Russia, the Newly Independent States (NIS), and the Baltic States (BS). The objective of the Department of Energy (DOE) Material Protection, Control, and Accounting Program (MPC and A) is to reduce the threat of nuclear proliferation by collaborating with Russia, NIS, and BS governments to promote western-style MPC and A. This cooperation will improve the MPC and A on all weapons useable nuclear materials and will establish a sustainable infrastructure to provide future support and maintenance for these technology-based improvements. Nuclear materials of proliferation concern include materials of the types and quantities that can be most easily and directly used in a nuclear weapon. Sabotage of nuclear material is an event of great concern and potentially disastrous consequences to both the US and the host country. However, sabotage is currently beyond the scope of program direction and cannot be used to justify US-funded MPC and A upgrades. Judicious MPC and A upgrades designed to protect against insider and outsider theft scenarios would also provide addition, although not comprehensive, protection against saboteurs. This paper provides some suggestions to establish consistency in prioritizing system-enhancement efforts at nuclear material facilities. The suggestions in this paper are consistent with DOE policy and directions and should be used as a supplement to any policy directives issued by NN-40, DOE Russia/NIS Task Force

  7. Nuclear materials control and accountability criteria for upgrades measures

    Energy Technology Data Exchange (ETDEWEB)

    Erkkila, B.H.; Hatcher, C.R.

    1998-11-01

    As a result of major political and societal changes in the past several years, methods of nuclear material control may no longer be as effective as in the past in Russia, the Newly Independent States (NIS), and the Baltic States (BS). The objective of the Department of Energy (DOE) Material Protection, Control, and Accounting Program (MPC and A) is to reduce the threat of nuclear proliferation by collaborating with Russia, NIS, and BS governments to promote western-style MPC and A. This cooperation will improve the MPC and A on all weapons useable nuclear materials and will establish a sustainable infrastructure to provide future support and maintenance for these technology-based improvements. Nuclear materials of proliferation concern include materials of the types and quantities that can be most easily and directly used in a nuclear weapon. Sabotage of nuclear material is an event of great concern and potentially disastrous consequences to both the US and the host country. However, sabotage is currently beyond the scope of program direction and cannot be used to justify US-funded MPC and A upgrades. Judicious MPC and A upgrades designed to protect against insider and outsider theft scenarios would also provide addition, although not comprehensive, protection against saboteurs. This paper provides some suggestions to establish consistency in prioritizing system-enhancement efforts at nuclear material facilities. The suggestions in this paper are consistent with DOE policy and directions and should be used as a supplement to any policy directives issued by NN-40, DOE Russia/NIS Task Force.

  8. Attributes identification of nuclear material by non-destructive radiation measurement methods

    International Nuclear Information System (INIS)

    Gan Lin

    2002-01-01

    Full text: The nuclear materials should be controlled under the regulation of National Safeguard System. The non-destructive analysis method, which is simple and quick, provide a effective process in determining the nuclear materials, nuclear scraps and wastes. The method play a very important role in the fields of nuclear material control and physical protection against the illegal removal and smuggling of nuclear material. The application of non-destructive analysis in attributes identification of nuclear material is briefly described in this paper. The attributes determined by radioactive detection technique are useful tolls to identify the characterization of special nuclear material (isotopic composition, enrichment etc.). (author)

  9. Measures to prevent, intercept and respond to illicit uses of nuclear material and radioactive sources. Proceedings

    International Nuclear Information System (INIS)

    2002-01-01

    As nuclear programmes have evolved, the quantities of nuclear material in use or storage, and the number of facilities operating or shut down has increased. In particular, the dismantling of nuclear weapons has resulted in greatly increased stockpiles of weapons usable plutonium and highly enriched uranium. Concern over the security of these and related materials has been further raised by the continued occurrence of cases of illicit trafficking. The risks are theft, leading to trafficking and possible illicit use, and sabotage which could lead to the creation of radiological hazards. The challenge is threefold: prevention, detection and interception, and response. Prevention starts with effective national systems for accountancy, control and protection. Detection and interception involves effective measures to combat illicit trafficking, and response requires planning for the consequences of theft and sabotage. Responsibilities in these fields are national, but nuclear security also has a powerful international dimension. The consequences of failures in national measures reach beyond national boundaries. The effectiveness of national nuclear security can be enhanced through international measures: through agreed international norms, standards and guides, through training and advice, through information exchange and the sharing of experience, and through developing common understandings and perceptions. The Stockholm Conference contributed by focusing on the threats, including terrorist, to nuclear and other radioactive materials; on how to assess them and on how to develop the appropriate security measures. National measures to protect nuclear material and facilities and the continuing development of international standards and obligations were described. The conference discussed the patterns and trends in the illicit trafficking of nuclear and other radioactive materials and national and international measures to combat such trafficking. Finally, it considered

  10. Measures to prevent, intercept and respond to illicit uses of nuclear material and radioactive sources. Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-08-01

    As nuclear programmes have evolved, the quantities of nuclear material in use or storage, and the number of facilities operating or shut down has increased. In particular, the dismantling of nuclear weapons has resulted in greatly increased stockpiles of weapons usable plutonium and highly enriched uranium. Concern over the security of these and related materials has been further raised by the continued occurrence of cases of illicit trafficking. The risks are theft, leading to trafficking and possible illicit use, and sabotage which could lead to the creation of radiological hazards. The challenge is threefold: prevention, detection and interception, and response. Prevention starts with effective national systems for accountancy, control and protection. Detection and interception involves effective measures to combat illicit trafficking, and response requires planning for the consequences of theft and sabotage. Responsibilities in these fields are national, but nuclear security also has a powerful international dimension. The consequences of failures in national measures reach beyond national boundaries. The effectiveness of national nuclear security can be enhanced through international measures: through agreed international norms, standards and guides, through training and advice, through information exchange and the sharing of experience, and through developing common understandings and perceptions. The Stockholm Conference contributed by focusing on the threats, including terrorist, to nuclear and other radioactive materials; on how to assess them and on how to develop the appropriate security measures. National measures to protect nuclear material and facilities and the continuing development of international standards and obligations were described. The conference discussed the patterns and trends in the illicit trafficking of nuclear and other radioactive materials and national and international measures to combat such trafficking. Finally, it considered

  11. Absolute nuclear material assay

    Science.gov (United States)

    Prasad, Manoj K [Pleasanton, CA; Snyderman, Neal J [Berkeley, CA; Rowland, Mark S [Alamo, CA

    2010-07-13

    A method of absolute nuclear material assay of an unknown source comprising counting neutrons from the unknown source and providing an absolute nuclear material assay utilizing a model to optimally compare to the measured count distributions. In one embodiment, the step of providing an absolute nuclear material assay comprises utilizing a random sampling of analytically computed fission chain distributions to generate a continuous time-evolving sequence of event-counts by spreading the fission chain distribution in time.

  12. Development of methods for measuring materials nuclear characteristics, Phases, I, II, II and IV

    International Nuclear Information System (INIS)

    Maglic, R.

    1963-04-01

    This report contains the following phases of the project 'measurement of nuclear characteristics of reactor materials': nuclear performances of the neutron chopper; method for measuring total effective cross sections by transmission method on the chopper; review of methods for measuring activation cross sections; measurement of neutron spectra of the RA reactor and measurement of total effective cross section of gold by using the chopper

  13. Uncertainty estimation in nuclear material weighing

    Energy Technology Data Exchange (ETDEWEB)

    Thaure, Bernard [Institut de Radioprotection et de Surete Nucleaire, Fontenay aux Roses, (France)

    2011-12-15

    The assessment of nuclear material quantities located in nuclear plants requires knowledge of additions and subtractions of amounts of different types of materials. Most generally, the quantity of nuclear material held is deduced from 3 parameters: a mass (or a volume of product); a concentration of nuclear material in the product considered; and an isotopic composition. Global uncertainties associated with nuclear material quantities depend upon the confidence level of results obtained in the measurement of every different parameter. Uncertainties are generally estimated by considering five influencing parameters (ISHIKAWA's rule): the material itself; the measurement system; the applied method; the environmental conditions; and the operator. A good practice guide, to be used to deal with weighing errors and problems encountered, is presented in the paper.

  14. Nuclear Security Systems and Measures for the Detection of Nuclear and Other Radioactive Material out of Regulatory Control. Implementing Guide (Arabic Edition)

    International Nuclear Information System (INIS)

    2015-01-01

    This publication provides guidance to Member States for the development, or improvement of nuclear security systems and measures for the detection of criminal or unauthorized acts with nuclear security implications involving nuclear and other radioactive material out of regulatory control. It describes the elements of an effective nuclear security detection architecture which is composed of an integrated set of nuclear security systems and measures, and is based on an appropriate legal and regulatory framework for the implementation of the national detection strategy. The publication is an implementing guide within the IAEA Nuclear Security Series and is intended for use by national policy makers, legislative bodies, competent authorities, institutions, and individuals involved in the establishment, implementation, maintenance or sustainability of nuclear security systems and measures for the detection of nuclear and other radioactive material out of regulatory control

  15. Measures for prevention illicit trafficking of nuclear and radioactive materials

    International Nuclear Information System (INIS)

    Strezov, A.

    2002-01-01

    Full text: In the early 1990ies the number of illicit trafficking cases with nuclear material and radioactive sources began to appear in the press more often than before. This fact became of great concern among international organizations and different states that the nuclear material subjected to trafficking might become in possession of rogue states and be implicated in weapons production or that stolen radioactive sources may cause health and safety effects to the population or to the environment. The creation and proposition of a model scheme procedure for the developing countries is important for starting the initial process of preventing and combating the illicit traffic of nuclear materials. Particular efforts have been directed for the protection of fissile materials. The reported incidents for diversion of nuclear materials have raised the problem of potential nuclear terrorism and also for countries of proliferation to take a short cut to the bomb. There is a need of rapid implementation of comprehensive, mutually reinforcing strategy to control the existing stockpiles of fissile material and to lower the future production and use of such materials. The illicit traffic of nuclear materials is a new threat, which requires new efforts, new approaches and coordination of services and institutions and even new legislation. The propositions of a model-procedure will allow better and quicker upgrade of developing countries capabilities for combating illicit nuclear trafficking. (author)

  16. Auditing nuclear materials statements

    International Nuclear Information System (INIS)

    Anon.

    1973-01-01

    A standard that may be used as a guide for persons making independent examinations of nuclear materials statements or reports regarding inventory quantities on hand, receipts, production, shipment, losses, etc. is presented. The objective of the examination of nuclear materials statements by the independent auditor is the expression of an opinion on the fairness with which the statements present the nuclear materials position of a nuclear materials facility and the movement of such inventory materials for the period under review. The opinion is based upon an examination made in accordance with auditing criteria, including an evaluation of internal control, a test of recorded transactions, and a review of measured discards and materials unaccounted for (MUF). The standard draws heavily upon financial auditing standards and procedures published by the American Institute of Certified Public Accountants

  17. The regulations concerning refining business of nuclear source material and nuclear fuel materials

    International Nuclear Information System (INIS)

    1979-01-01

    The regulations are provided for under the law for the regulations of nuclear source materials, nuclear fuel materials and reactors and provisions concerning refining business in the enforcement order for the law. The basic concepts and terms are defined, such as: exposure dose, accumulative dose; controlled area; inspected surrounding area and employee. Refining facilities listed in the application for designation shall be classified into clushing and leaching, thickning, refining facilities, storage facilities of nuclear source materials and nuclear fuel materials, disposal facilities of contaminated substances and building for refining, etc. Business program attached to the application shall include expected time of beginning of refining, estimated production amount of nuclear source materials or nuclear fuel materials for the first three years and funds necessary for construction, etc. Records shall be made and kept for particular periods on delivery and storage of nuclear source materials and nuclear fuel materials, control of radiation, maintenance and accidents of refining facilities. Safety securing, application of internationally regulated substances and measures in dangerous situations are stipulated respectively. Exposure dose of employees and other specified matters shall be reported by the refiner yearly to the Director General of Science and Technology Agency and the Minister of International Trade and Industry. (Okada, K.)

  18. Nuclear measurements and reference materials annual progress report, january - december 1988

    International Nuclear Information System (INIS)

    1989-01-01

    The 1988 progress report of the Central Bureau for Nuclear Measurements (CBNM) is presented. The major changes in the role and orientation of the Joint Research Center, of which CBNM is an institute, are included. The main tasks of CBNM, which involve the program on Nuclear Measurements and Reference Materials, are given. Technical activities concerning the GELINA electron beam and Van de Graaff accelerators are reported. The study of transition radiation at linear electron accelerators, and the development of isotope dilution mass spectrometry, for trace analysis and isotope abundance measurements in iron and gallium, are summarized. The scientific and technical support to the commission, work for third parties, and contribution to conferences are presented

  19. Nuclear measurements

    International Nuclear Information System (INIS)

    Schenkel, R.

    2005-01-01

    Nuclear measurements play a fundamental role in the development of nuclear technology and the assurance of its peaceful use. They are also required in many non-power nuclear applications such as in nuclear medicine, agriculture, environmental protection, etc. This presentation will show examples of most recent advances in measurement methodology or technology in the areas described below. The Generation IV International Forum has selected six innovative reactor systems as candidates for a next generation of sustainable, economic and safe nuclear energy systems. The choice of the best options relies heavily on the availability of accurate nuclear data that can only be obtained, in an international effort, using highly specialised facilities. Significant efforts are being directed towards the partitioning and transmutation of highly active nuclear waste. Different concepts involving fast reactors or accelerator-driven systems are being studied in view of their transmutation capabilities. State of the art equipment has been developed to assess basic properties of nuclear fuel at very high burn-up; some fine examples of this work will be shown. Physical and chemical methods play a crucial role in the detection and identification of radioisotopes used in various stages of the nuclear fuel cycle. Radiation measurement techniques are used, for example, to monitor the quantities of uranium, plutonium and other actinide elements in fuel enrichment and reprocessing facilities. Another field of application of physical and chemical methods is the characterisation of nuclear material seized from illicit trafficking. Seized material has to be analysed in order to obtain clues on its origin and intended use and to prevent diversion of nuclear material from the same source in the future. A recent highlight in basic physics relates to nuclear fission and transmutation with high intensity lasers. Ultra-fast high intensity lasers can produce high energy (tens of MeV) photons through

  20. US-Russian Cooperation in Upgrading MC and A System at Rosatom Facilities: Measurement of Nuclear Materials

    International Nuclear Information System (INIS)

    Powell, Danny H.; Jensen, Bruce A.

    2011-01-01

    Improve protection of weapons-usable nuclear material from theft or diversion through the development and support of a nationwide sustainable and effective Material Control and Accountability (MC and A) program based on material measurement. The material protection, control, and accountability (MPC and A) cooperation has yielded significant results in implementing MC and A measurements at Russian nuclear facilities: (1) Establishment of MEM WG and MEMS SP; (2) Infrastructure for development, certification, and distribution of RMs; and (3) Coordination on development and implementation of MMs.

  1. 1981 Annual status report. Nuclear measurements

    International Nuclear Information System (INIS)

    1982-01-01

    The Nuclear Measurements programme is divided into two main projects, Nuclear Data on the one hand and Nuclear Reference Materials and Techniques on the other. In the former the JRC actions form part of world-wide sets of actions to establish reliable, and in many cases very precise, figures for important nuclear parameters - e.g. neutron interaction cross-sections, radio-nuclide half lives. In this work the Central Bureau for Nuclear Measurements (CBNM) pays particular attention to the specific needs of the Community and to complement similar actions undertaken in the laboratories belonging to the Member States. Concerning Nuclear Reference Materials and Techniques the actions are to provide materials to which analytical and other measurements carried out in the nuclear industry or by the nuclear community can be referred. The basic aim of the Nuclear measurement programme is therefore to develop nuclear metrology with special orientation towards satisfying the demands for basic nuclear data and for materials and methods or reference

  2. International Target Values 2010 for Measurement Uncertainties in Safeguarding Nuclear Materials

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-12-15

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

  3. Passive nondestructive assay of nuclear materials

    International Nuclear Information System (INIS)

    Reilly, D.; Ensslin, N.; Smith, H. Jr.; Kreiner, S.

    1991-03-01

    The term nondestructive assay (NDA) is applied to a series of measurement techniques for nuclear fuel materials. The techniques measure radiation induced or emitted spontaneously from the nuclear material; the measurements are nondestructive in that they do not alter the physical or chemical state of the nuclear material. NDA techniques are characterized as passive or active depending on whether they measure radiation from the spontaneous decay of the nuclear material or radiation induced by an external source. This book emphasizes passive NDA techniques, although certain active techniques like gamma-ray absorption densitometry and x-ray fluorescence are discussed here because of their intimate relation to passive assay techniques. The principal NDA techniques are classified as gamma-ray assay, neutron assay, and calorimetry. Gamma-ray assay techniques are treated in Chapters 1--10. Neutron assay techniques are the subject of Chapters 11--17. Chapters 11--13 cover the origin of neutrons, neutron interactions, and neutron detectors. Chapters 14--17 cover the theory and applications of total and coincidence neutron counting. Chapter 18 deals with the assay of irradiated nuclear fuel, which uses both gamma-ray and neutron assay techniques. Chapter 19 covers perimeter monitoring, which uses gamma-ray and neutron detectors of high sensitivity to check that no unauthorized nuclear material crosses a facility boundary. The subject of Chapter 20 is attribute and semiquantitative measurements. The goal of these measurements is a rapid verification of the contents of nuclear material containers to assist physical inventory verifications. Waste and holdup measurements are also treated in this chapter. Chapters 21 and 22 cover calorimetry theory and application, and Chapter 23 is a brief application guide to illustrate which techniques can be used to solve certain measurement problems

  4. The regulations concerning refining business of nuclear source material and nuclear fuel materials

    International Nuclear Information System (INIS)

    1981-01-01

    This rule is established under the provisions concerning refining business in the law concerning the regulation of nuclear raw materials, nuclear fuel materials and nuclear reactors and the ordinance for the execution of this law, and to enforce them. Basic terms are defined, such as: exposure radiation dose, cumulative dose, control area, surrounding monitoring area and worker. The application for the designation for refining business under the law shall be classified into the facilities for crushing and leaching-filtration, thikening, and refining, the storage facilities for nuclear raw materials and nuclear fuel materials, and the disposal facilities for radioactive wastes, etc. To the application, shall be attached business plans, the explanations concerning the technical abilities of applicants and the prevention of hazards by nuclear raw materials and nuclear fuel materials regarding refining facilities, etc. Records shall be made on the accept, delivery and stock of each kind of nuclear raw materials and nuclear fuel materials, radiation control, the maintenance of and accidents in refining facilities, and kept for specified periods, respectively. Security regulations shall be enacted for each works or enterprise on the functions and organizations of persons engaged in the control of refining facilities, the operation of the apparatuses which must be controlled for the prevention of accidents, and the establishment of control area and surrounding monitoring area, etc. The report on the usage of internationally regulated goods and the measures taken at the time of danger are defined particularly. (Okada, K.)

  5. Measures against illicit trafficking of nuclear material and radioactive sources in the Republic of Belarus

    International Nuclear Information System (INIS)

    Piotoukh, O.

    2001-01-01

    Full text: The Republic of Belarus strives to take an active part in international cooperation in the field of prevention and interception of illicit uses of nuclear material and radioactive sources through: multilateral international agreements and bilateral interagency treatments; information exchange within the IAEA Illicit Trafficking Database; participation in different international seminars, workshops, conferences including those under the IAEA auspices etc. Belarus is constantly improving regulatory, legal and technical aspects of activities aimed at: accounting, control and ensuring of physical protection of nuclear material and security of radioactive sources; exercising efficient control over their export and import; detecting cases of their illicit uses and illegal cross-border movements and informing of such cases through the IAEA Illicit Trafficking Database; developing and providing training opportunities for personnel. Through Resolution 'On Measures for Physical Protection of Nuclear Materials' issued by the Council of Ministers in 1993, Committee for Supervision of Industrial and Nuclear Safety (PROMATOMNADZOR) was appointed as the authority responsible for ensuring physical protection of nuclear materials and facilities. Through Resolution 'On Measures for Fulfillment of Provisions of the Non-Proliferation Treaty' issued by the Council of Ministers in 1993, Promatomnadzor was designated as the national competent authority responsible for the establishment and maintenance of the State System of Accounting and Control of nuclear material. The system accounts all the nuclear material meeting the criteria defined in the Safeguards Agreement with the IAEA. The system includes two levels: i.e. on-site accounting and control and state accounting and control exercised by Promatomnadzor. Apart from reporting to the Agency, the system also provides for national tasks being accomplished: control over uses of nuclear material, its physical protection, access

  6. Protection and control of nuclear materials

    International Nuclear Information System (INIS)

    Jalouneix, J.; Winter, D.

    2007-01-01

    In the framework of the French regulation on nuclear materials possession, the first liability is the one of operators who have to know at any time the quantity, quality and localization of any nuclear material in their possession. This requires an organization of the follow up and of the inventory of these materials together with an efficient protection against theft or sabotage. The French organization foresees a control of the implementation of this regulation at nuclear facilities and during the transport of nuclear materials by the minister of industry with the sustain of the institute of radiation protection and nuclear safety (IRSN). This article presents this organization: 1 - protection against malevolence; 2 - national protection and control of nuclear materials: goals, administrative organization, legal and regulatory content (authorization, control, sanctions), nuclear materials protection inside facilities (physical protection, follow up and inventory, security studies), protection of nuclear material transports (physical protection, follow up), control of nuclear materials (inspection at facilities, control of nuclear material measurements, inspection of nuclear materials during transport); 3 - international commitments of France: non-proliferation treaty, EURATOM regulation, international convention on the physical protection of nuclear materials, enforcement in France. (J.S.)

  7. Tracer techniques in estimating nuclear materials holdup

    International Nuclear Information System (INIS)

    Pillay, K.K.S.

    1987-01-01

    Residual inventory of nuclear materials remaining in processing facilities (holdup) is recognized as an insidious problem for safety of plant operations and safeguarding of special nuclear materials (SNM). This paper reports on an experimental study where a well-known method of radioanalytical chemistry, namely tracer technique, was successfully used to improve nondestructive measurements of holdup of nuclear materials in a variety of plant equipment. Such controlled measurements can improve the sensitivity of measurements of residual inventories of nuclear materials in process equipment by several orders of magnitude and the good quality data obtained lend themselves to developing mathematical models of holdup of SNM during stable plant operations

  8. 1982 annual status report. Nuclear measurements

    International Nuclear Information System (INIS)

    1983-01-01

    The Nuclear Measurement programme is briefly presented in this status report, it is divided in two main projects, Nuclear Data on the one hand (neutron data, non neutron nuclear data) and Nuclear Reference Materials and Techniques on the other (nuclear reference materials, samples and targets for nuclear measurements, development of reference techniques, study for the production of enriched actinide isotopes)

  9. Nuclear material management: challenges and prospects

    International Nuclear Information System (INIS)

    Rieu, J.; Besnainou, J.; Leboucher, I.; Chiguer, M.; Capus, G.; Greneche, D.; Durret, L.F.; Carbonnier, J.L.; Delpech, M.; Loaec, Ch.; Devezeaux de Lavergne, J.G.; Granger, S.; Devid, S.; Bidaud, A.; Jalouneix, J.; Toubon, H.; Pochon, E.; Bariteau, J.P.; Bernard, P.; Krellmann, J.; Sicard, B.

    2008-01-01

    The articles in this dossier were derived from the papers of the yearly S.F.E.N. convention, which took place in Paris, 12-13 March 2008. They deal with the new challenges and prospects in the field of nuclear material management, throughout the nuclear whole fuel cycle, namely: the institutional frame of nuclear materials management, the recycling, the uranium market, the enrichment market, the different scenarios for the management of civil nuclear materials, the technical possibilities of spent fuels utilization, the option of thorium, the convention on the physical protection of nuclear materials and installations, the characterisation of nuclear materials by nondestructive nuclear measurements, the proliferation from civil installations, the use of plutonium ( from military origin) and the international agreements. (N.C.)

  10. Illicit diversion of nuclear materials

    International Nuclear Information System (INIS)

    Bett, F.L.

    1975-08-01

    This paper discusses the means of preventing illegal use of nuclear material by terrorists or other sub-national groups and by governments. With respect to sub-national groups, it concludes that the preventive measures of national safeguards systems, when taken together with the practical difficulties of using nuclear material, would make the diversion and illegal use of nuclear material unattractive in comparison with other avenues open to these groups to attain their ends. It notes that there are only certain areas in the nuclear fuel cycle, e.g. production of some types of nuclear fuel embodying highly enriched uranium and shipment of strategically significant nuclear material, which contain material potentially useful to these groups. It also discusses the difficult practical problems, e.g. coping with radiation, which would face the groups in making use of the materials for terrorist purposes. Concerning illegal use by Governments, the paper describes the role of international safeguards, as applied by the International Atomic Energy Agency, and the real deterrent effect of these safeguards which is achieved through the requirements to maintain comprehensive operating records of the use of nuclear material and by regular inspections to verify these records. The paper makes the point that Australia would not consider supplying nuclear material unless it were subject to international safeguards. (author)

  11. Nuclear data of the major actinide fuel materials

    Energy Technology Data Exchange (ETDEWEB)

    Poenitz, W.P.; Saussure, G. De

    1984-01-01

    The effect of nuclear data of the major actinide fuel materials on the design accuracy, economics and safety of nuclear power systems is discussed. Since most of the data are measured relative to measurement standards, in particular the fission cross-section of /sup 235/U, data must be examined to ensure that absolute measurements and relative measurements are correctly handled. Nuclear data of fissile materials, fertile materials and minor plutonium isotopes are discussed.

  12. 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.

  13. 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

  14. The choice of nuclear material measurement strategy in bulk-form in material balance area

    International Nuclear Information System (INIS)

    Smirnov, V.M.; Sergeev, S.A.; Kirsanov, V.S.

    1999-01-01

    Concepts have been defined such as Shipment batch, Technological batch, and Accounting batch, it has been found that Shipment and Technological batches should be formed through the arrangement of group of measured Accounting batches. The strategy for nuclear material (NM) measurement based on the Accounting batch is shown to give a possibility to use the advantages for the accounting purposes: ensure safeguards of non-diversion of NM at quantitative (numerical) level, which is a higher grade of safeguards compared to the systems of accounting and control now in force of the US and EURATOM; ensure a guaranteed accuracy and reliability (confidence level) when making up NM balance in Material Balance Area (MBA) and at Federal level, which has been realized only in part in the NM control and accounting systems. Strategy of NM measurement for MBAs counting NM in bulk form has been proposed [ru

  15. International target values 2010 for achievable measurement uncertainties in nuclear material accountancy

    Energy Technology Data Exchange (ETDEWEB)

    Dias, Fabio C., E-mail: fabio@ird.gov.b [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil); Almeida, Silvio G. de; Renha Junior, Geraldo, E-mail: silvio@abacc.org.b, E-mail: grenha@abacc.org.b [Agencia Brasileiro-Argentina de Contabilidade e Controle de Materiais Nucleares (ABACC), Rio de Janeiro, RJ (Brazil)

    2011-07-01

    The International Target Values (ITVs) are reasonable uncertainty estimates that can be used in judging the reliability of measurement techniques applied to industrial nuclear and fissile materials subject to accountancy and/or safeguards verification. In the absence of relevant experimental estimates, ITVs can also be used to select measurement techniques and calculate sample population during the planning phase of verification activities. It is important to note that ITVs represent estimates of the 'state-of-the-practice', which should be achievable under routine measurement conditions affecting both facility operators and safeguards inspectors, not only in the field, but also in laboratory. Tabulated values cover measurement methods used for the determination of volume or mass of the nuclear material, for its elemental and isotopic assays, and for its sampling. The 2010 edition represents the sixth revision of the International Target Values (ITVs), issued by the International Atomic Energy Agency (IAEA) as a Safeguards Technical Report (STR-368). The first version was released as 'Target Values' in 1979 by the Working Group on Techniques and Standards for Destructive Analysis (WGDA) of the European Safeguards Research and Development Association (ESARDA) and focused on destructive analytical methods. In the latest 2010 revision, international standards in estimating and expressing uncertainties have been considered while maintaining a format that allows comparison with the previous editions of the ITVs. Those standards have been usually applied in QC/QA programmes, as well as qualification of methods, techniques and instruments. Representatives of the Brazilian Nuclear Energy Commission (CNEN) and the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC) participated in previous Consultants Group Meetings since the one convened to establish the first list of ITVs released in 1993 and in subsequent revisions

  16. International target values 2010 for achievable measurement uncertainties in nuclear material accountancy

    International Nuclear Information System (INIS)

    Dias, Fabio C.; Almeida, Silvio G. de; Renha Junior, Geraldo

    2011-01-01

    The International Target Values (ITVs) are reasonable uncertainty estimates that can be used in judging the reliability of measurement techniques applied to industrial nuclear and fissile materials subject to accountancy and/or safeguards verification. In the absence of relevant experimental estimates, ITVs can also be used to select measurement techniques and calculate sample population during the planning phase of verification activities. It is important to note that ITVs represent estimates of the 'state-of-the-practice', which should be achievable under routine measurement conditions affecting both facility operators and safeguards inspectors, not only in the field, but also in laboratory. Tabulated values cover measurement methods used for the determination of volume or mass of the nuclear material, for its elemental and isotopic assays, and for its sampling. The 2010 edition represents the sixth revision of the International Target Values (ITVs), issued by the International Atomic Energy Agency (IAEA) as a Safeguards Technical Report (STR-368). The first version was released as 'Target Values' in 1979 by the Working Group on Techniques and Standards for Destructive Analysis (WGDA) of the European Safeguards Research and Development Association (ESARDA) and focused on destructive analytical methods. In the latest 2010 revision, international standards in estimating and expressing uncertainties have been considered while maintaining a format that allows comparison with the previous editions of the ITVs. Those standards have been usually applied in QC/QA programmes, as well as qualification of methods, techniques and instruments. Representatives of the Brazilian Nuclear Energy Commission (CNEN) and the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC) participated in previous Consultants Group Meetings since the one convened to establish the first list of ITVs released in 1993 and in subsequent revisions, including the latest one

  17. Nuclear measurements in industry

    International Nuclear Information System (INIS)

    Rozsa, S.

    1989-01-01

    In this book the author provides a description of nuclear measurements in industry, covering the physical principles, methods, instruments and equipment, and industrial applications. One of the great advantages of industrial nuclear measurements is that their use ensures the optimum use of raw material. The increasing cost of raw materials makes it essential to adhere strictly to the standards and prescriptions related to the product and this is possible only by the application of continuous and accurate measurements. As a result, the importance of nuclear instruments is rapidly growing particularly in fields where the application of alternative methods is not possible. This is illustrated by several practical examples described in the book. Similarly important are nuclear measuring the process control equipment which serve to optimize the use of energy in industrial processes

  18. Nuclear Materials Management. Proceedings of the Symposium on Nuclear Materials Management

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1966-02-15

    An increasing number of countries are using nuclear materials which, because of their high value and the potential hazards involved, require special methods of handling. To discuss these and to provide a forum at which different systems for achieving the necessary economy and safety could be compared, the International Atomic Energy Agency held a Symposium at Vienna on Nuclear Materials Management from 30 August to 3 September, 1965. It was attended by 115 participants from 19 Member States and two international organizations. Nuclear materials are already being used on an industrial scale and their high cost demands close and continuous control to ensure that they are delivered precisely on time and that they are used to the fullest possible extent before they are withdrawn from service. Routine industrial methods of material control and verification are widely used to ensure safe and economical operation and handling in nuclear power stations, in fuel-element fabrication and reprocessing plants, and in storage facilities. In addition special refinements are needed to take account of the value and the degree of purity required of nuclear materials. Quality as well as quantity has to be checked thoroughly and the utmost economy in processing is necessary. The radioactivity of the material poses special problems of handling and storage and creates a potential hazard to health. A further problem is that of criticality. These dangers and the means of averting them are well understood, as is evidenced by the outstandingly good safety record of the atomic energy industry. But besides accommodating all these special problems, day-to-day procedures must be simple enough to fit in with industrial conditions. Many of the 58 papers presented at the Symposium emphasized that records, checks, measurements and handling precautions, if suitably devised, provide the control vital to efficient operation, serve as checks against loss or waste of valuable materials and help meet the

  19. The Physical Protection of Nuclear Material and Nuclear Facilities

    International Nuclear Information System (INIS)

    1999-08-01

    Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international co-operation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and nuclear materials, particularly when such materials are transported across national frontiers

  20. The Physical Protection of Nuclear Material and Nuclear Facilities

    International Nuclear Information System (INIS)

    1999-06-01

    Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international co-operation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and nuclear materials, particularly when such materials are transported across national frontiers [es

  1. The Physical Protection of Nuclear Material and Nuclear Facilities

    International Nuclear Information System (INIS)

    1999-06-01

    Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international co-operation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and nuclear materials, particularly when such materials are transported across national frontiers

  2. A novel method to assay special nuclear materials by measuring prompt neutrons from polarized photofission

    Energy Technology Data Exchange (ETDEWEB)

    Mueller, J.M., E-mail: mueller@tunl.duke.edu [Triangle Universities Nuclear Laboratory, Durham, NC 27710 (United States); Department of Physics, Duke University, Durham, NC 27708 (United States); Ahmed, M.W. [Triangle Universities Nuclear Laboratory, Durham, NC 27710 (United States); Department of Physics, Duke University, Durham, NC 27708 (United States); Department of Mathematics and Physics, North Carolina Central University, Durham, NC 27707 (United States); Weller, H.R. [Triangle Universities Nuclear Laboratory, Durham, NC 27710 (United States); Department of Physics, Duke University, Durham, NC 27708 (United States)

    2014-08-01

    A novel method of measuring the enrichment of special nuclear material is presented. Recent photofission measurements using a linearly polarized γ-ray beam were performed on samples of {sup 232}Th, {sup 233,235,238}U, {sup 237}Np, and {sup 239,240}Pu. Prompt neutron polarization asymmetries, defined to be the difference in the prompt neutron yields parallel and perpendicular to the plane of beam polarization divided by their sum, were measured. It was discovered that the prompt neutron polarization asymmetries differed significantly depending on the sample. Prompt neutrons from photofission of even–even (non-fissile) targets had significant polarization asymmetries (∼0.2 to 0.5), while those from odd-A (generally fissile) targets had polarization asymmetries close to zero. This difference in the polarization asymmetries could be exploited to measure the fissile versus non-fissile content of special nuclear materials, and potentially to detect the presence of fissile material during active interrogation. The proposed technique, its expected performance, and its potential applicability are discussed.

  3. A novel method to assay special nuclear materials by measuring prompt neutrons from polarized photofission

    International Nuclear Information System (INIS)

    Mueller, J.M.; Ahmed, M.W.; Weller, H.R.

    2014-01-01

    A novel method of measuring the enrichment of special nuclear material is presented. Recent photofission measurements using a linearly polarized γ-ray beam were performed on samples of 232 Th, 233,235,238 U, 237 Np, and 239,240 Pu. Prompt neutron polarization asymmetries, defined to be the difference in the prompt neutron yields parallel and perpendicular to the plane of beam polarization divided by their sum, were measured. It was discovered that the prompt neutron polarization asymmetries differed significantly depending on the sample. Prompt neutrons from photofission of even–even (non-fissile) targets had significant polarization asymmetries (∼0.2 to 0.5), while those from odd-A (generally fissile) targets had polarization asymmetries close to zero. This difference in the polarization asymmetries could be exploited to measure the fissile versus non-fissile content of special nuclear materials, and potentially to detect the presence of fissile material during active interrogation. The proposed technique, its expected performance, and its potential applicability are discussed

  4. Measurement control workshop instructional materials

    Energy Technology Data Exchange (ETDEWEB)

    Gibbs, Philip [Brookhaven National Lab. (BNL), Upton, NY (United States); Harvel, Charles [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Clark, John [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Gregg Protection Services, Lynchburg, VA (United States)

    2012-09-01

    An essential element in an effective nuclear materials control and accountability (MC&A) program is the measurement of the nuclear material as it is received, moved, processed and shipped. Quality measurement systems and methodologies determine the accuracy of the accountability values. Implementation of a measurement control program is essential to ensure that the measurement systems and methodologies perform as expected. A measurement control program also allows for a determination of the level of confidence in the accounting values.

  5. Measurement control workshop instructional materials

    Energy Technology Data Exchange (ETDEWEB)

    Gibbs, Philip [Brookhaven National Lab. (BNL), Upton, NY (United States); Harvel, Charles [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Clark, John [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Gregg Protection Services, Lynchburg, VA (United States)

    2011-12-01

    An essential element in an effective nuclear materials control and accountability (MC&A) program is the measurement of the nuclear material as it is received, moved, processed and shipped. Quality measurement systems and methodologies determine the accuracy of the accountability values. Implementation of a measurement control program is essential to ensure that the measurement systems and methodologies perform as expected. A measurement control program also allows for a determination of the level of confidence in the ac counting values.

  6. 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.

  7. Approaches to characterization of nuclear material for establishment of nuclear forensics

    International Nuclear Information System (INIS)

    Okazaki, Hiro; Sumi, Mika; Sato, Mitsuhiro; Kayano, Masashi; Kageyama, Tomio; Shinohara, Nobuo; Martinez, Patrick; Xu, Ning; Thomas, Mariam; Porterfield, Donivan; Colletti, Lisa; Schwartz, Dan; Tandon, Lav

    2014-01-01

    The Plutonium Fuel Development Center (PFDC) of Japan Atomic Energy Agency has been analyzing isotopic compositions and contents of plutonium and uranium as well as trace impurities and physics in the nuclear fuel from MOX fuel fabrication process for accountancy and process control purpose. These analytical techniques are also effective for nuclear forensics to identify such as source, history, and route of the material by determining a composition and characterization of nuclear material. Therefore, PFDC cooperates with Los Alamos National Laboratory which has broad experience and established measurement skill for nuclear forensics, and evaluates the each method, procedure and analytical data toward R and D of characterizing a nuclear material for forensic purposes. This paper describes the approaches to develop characterization techniques of nuclear material for nuclear forensics purposes at PFDC. (author)

  8. Nuclear materials

    International Nuclear Information System (INIS)

    1996-01-01

    In 1998, Nuclear Regulatory Authority of the Slovak Republic (NRA SR) performed 38 inspections, 25 of them were performed in co-operation with IAEA inspectors. There is no fresh nuclear fuel at Bohunice A-1 NPP at present. Fresh fuel of Bohunice V-1 and V-2 NPPs is inspected in the fresh fuel storage.There are 327 fresh fuel assemblies in Mochovce NPP fresh fuel storage. In addition to that, are also 71 small users of nuclear materials in Slovakia. In most cases they use: covers made of depleted uranium for non-destructive works, detection of level in production plants, covers for therapeutical sources at medical facilities. In. 1995, NRA SR issued 4 new licences for nuclear material withdrawal. In the next part manipulation with nuclear materials, spent fuel stores and illegal trafficking in nuclear materials are reported

  9. Supplier responsibility for nuclear material quality

    International Nuclear Information System (INIS)

    Stuart, P.S.; Dohna, A.E.

    1976-01-01

    Nuclear materials must be delivered by either the manufacturer or the distributor with objective, documented evidence that the material was manufactured, inspected, and tested by proven techniques performed by qualified personnel working to documented procedures. Measurement devices used for acceptance must be of proven accuracy. The material and all records must be identified for positive traceability as part of the quality history of the nuclear components, system, or structure in which the material was used. In conclusion, the nuclear material supplier must join the fabricator, the installer, and the user in effective implementation of the total systems approach to the application of quality assurance principles to all phases of procurement, fabrication, installation, and use of the safety-related components, systems, and structures in a nuclear power plant

  10. Nuclear material statistical accountancy system

    International Nuclear Information System (INIS)

    Argentest, F.; Casilli, T.; Franklin, M.

    1979-01-01

    The statistical accountancy system developed at JRC Ispra is refered as 'NUMSAS', ie Nuclear Material Statistical Accountancy System. The principal feature of NUMSAS is that in addition to an ordinary material balance calcultation, NUMSAS can calculate an estimate of the standard deviation of the measurement error accumulated in the material balance calculation. The purpose of the report is to describe in detail, the statistical model on wich the standard deviation calculation is based; the computational formula which is used by NUMSAS in calculating the standard deviation and the information about nuclear material measurements and the plant measurement system which are required as data for NUMSAS. The material balance records require processing and interpretation before the material balance calculation is begun. The material balance calculation is the last of four phases of data processing undertaken by NUMSAS. Each of these phases is implemented by a different computer program. The activities which are carried out in each phase can be summarised as follows; the pre-processing phase; the selection and up-date phase; the transformation phase, and the computation phase

  11. 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.)

  12. Development of nuclear material accountancy control system

    International Nuclear Information System (INIS)

    Hirosawa, Naonori; Kashima, Sadamitsu; Akiba, Mitsunori

    1992-01-01

    PNC is developing a wide area of nuclear fuel cycle. Therefore, much nuclear material with a various form exists at each facility in the Works, and the controls of the inventory changes and the physical inventories of nuclear material are important. Nuclear material accountancy is a basic measure in safeguards system based on Non-Proliferation Treaty (NPT). In the light of such importance of material accountancy, the data base of nuclear material control and the material accountancy report system for all facilities has been developed by using the computer. By this system, accountancy report to STA is being presented certainly and timely. Property management and rapid corresponding to various inquiries can be carried out by the data base system which has free item searching procedure. (author)

  13. Regulation on control of nuclear fuel materials

    International Nuclear Information System (INIS)

    Ikeda, Kaname

    1976-01-01

    Some comment is made on the present laws and the future course of consolidating the regulation of nuclear fuel materials. The first part gives the definitions of the nuclear fuel materials in the laws. The second part deals with the classification and regulation in material handling. Refinement undertaking, fabrication undertaking, reprocessing undertaking, the permission of the government to use the materials, the permission of the government to use the materials under international control, the restriction of transfer and receipt, the reporting, and the safeguard measures are commented. The third part deals with the strengthening of regulation. The nuclear fuel safety deliberation special committee will be established at some opportunity of revising the ordinance. The nuclear material safeguard special committee has been established in the Atomic Energy Commission. The last part deals with the future course of legal consolidation. The safety control will be strengthened. The early investigation of waste handling is necessary, because low level solid wastes are accumulating at each establishment. The law for transporting nuclear materials must be consolidated as early as possible to correspond to foreign transportation laws. Physical protection is awaiting the conclusions of the nuclear fuel safeguard special committee. The control and information systems for the safeguard measures must be consolidated in the laws. (Iwakiri, K.)

  14. The U.S. national nuclear forensics library, nuclear materials information program, and data dictionary

    International Nuclear Information System (INIS)

    Lamont, Stephen Philip; Brisson, Marcia; Curry, Michael

    2011-01-01

    Nuclear forensics assessments to determine material process history requires careful comparison of sample data to both measured and modeled nuclear material characteristics. Developing centralized databases, or nuclear forensics libraries, to house this information is an important step to ensure all relevant data will be available for comparison during a nuclear forensics analysis and help expedite the assessment of material history. The approach most widely accepted by the international community at this time is the implementation of National Nuclear Forensics libraries, which would be developed and maintained by individual nations. This is an attractive alternative toan international database since it provides an understanding that each country has data on materials produced and stored within their borders, but eliminates the need to reveal any proprietary or sensitive information to other nations. To support the concept of National Nuclear Forensics libraries, the United States Department of Energy has developed a model library, based on a data dictionary, or set of parameters designed to capture all nuclear forensic relevant information about a nuclear material. Specifically, information includes material identification, collection background and current location, analytical laboratories where measurements were made, material packaging and container descriptions, physical characteristics including mass and dimensions, chemical and isotopic characteristics, particle morphology or metallurgical properties, process history including facilities, and measurement quality assurance information. While not necessarily required, it may also be valuable to store modeled data sets including reactor burn-up or enrichment cascade data for comparison. It is fully expected that only a subset of this information is available or relevant to many materials, and much of the data populating a National Nuclear Forensics library would be process analytical or material accountability

  15. 10 CFR 74.31 - Nuclear material control and accounting for special nuclear material of low strategic significance.

    Science.gov (United States)

    2010-01-01

    ... and maintain a measurement system which assures that all quantities in the material accounting records...) In each inventory period, control total material control and accounting measurement uncertainty so... 10 Energy 2 2010-01-01 2010-01-01 false Nuclear material control and accounting for special...

  16. Evaluating the attractiveness of nuclear material for proliferation-resistance and nuclear security

    International Nuclear Information System (INIS)

    Choi, Jor-Shan; Ikegame, Kou; Kuno, Yusuke

    2011-01-01

    The attractiveness of nuclear material, defined as a function of the isotopic composition of the nuclear material in formulas expressing the material's intrinsic properties, is of considerably debate in recent developments of proliferation-resistance measures of a nuclear energy system. A reason for such debate arises from the fact that the concept of nuclear material attractiveness can be confusing because the desirability of a material for nuclear explosive use depends on many tangible and intangible factors including the intent and capability of the adversary. In addition, a material that is unattractive to an advanced nation (in the case of proliferation) may be very attractive to a terrorist (in the case of physical protection and nuclear security). Hence, the concept of 'Nuclear Material Attractiveness' for different nuclear materials must be considered in the context of safeguards and security. The development of a ranking scheme on the attractiveness of nuclear materials could be a useful concept to start-off the strategies for safeguards and security on a new footing (i.e., why and how nuclear material is attractive, and what are the quantifiable basis). Japan may benefit from such concept regarding the attractiveness of nuclear materials when recovering nuclear materials from the damaged cores in Fukushima because safety, security, and safeguards (3S) would be a prominent consideration for the recovery operation, and it would be the first time such operation is performed in a non-nuclear weapons state. (author)

  17. Comprehensive nuclear materials

    CERN Document Server

    Allen, Todd; Stoller, Roger; Yamanaka, Shinsuke

    2012-01-01

    Comprehensive Nuclear Materials encapsulates a panorama of fundamental information on the vast variety of materials employed in the broad field of nuclear technology. The work addresses, in five volumes, 3,400 pages and over 120 chapter-length articles, the full panorama of historical and contemporary international research in nuclear materials, from Actinides to Zirconium alloys, from the worlds' leading scientists and engineers. It synthesizes the most pertinent research to support the selection, assessment, validation and engineering of materials in extreme nuclear environments. The work discusses the major classes of materials suitable for usage in nuclear fission, fusion reactors and high power accelerators, and for diverse functions in fuels, cladding, moderator and control materials, structural, functional, and waste materials.

  18. Risk Prevention for Nuclear Materials and Radioactive Sources

    International Nuclear Information System (INIS)

    Badawy, I.

    2008-01-01

    The present paper investigates the parameters which may have effects on the safety of nuclear materials and other radioactive sources used in peaceful applications of atomic energy. The emergency response planning in such situations are also indicated. In synergy with nuclear safety measures, an approach is developed in this study for risk prevention. It takes into consideration the collective implementation of measures of nuclear material accounting and control, physical protection and monitoring of such strategic and dangerous materials in an integrated and coordinated real-time mode at a nuclear or radiation facility and in any time

  19. Definition of Nuclear Material in Aspects of Nuclear Nonproliferation and Security

    International Nuclear Information System (INIS)

    Jeon, Ji Hye; Lee, Chan Suh

    2014-01-01

    Nuclear safety accidents directly affect human health but nuclear security incidents indirectly influence human, which demonstrates the reason why security receives less attention. However, it is acknowledged that nuclear terrorism is indeed one of the most dreadful threat humanity faces. As part of strengthening nuclear security as well as nonproliferation to response to the threat, we need a better understanding of the nuclear material which needs to be safe under the objective of nuclear security. In reality, practitioners implement safeguards and physical protection in compliance with the regulation text in domestic legislation. Thus, it is important to specify nuclear material clearly in law for effective implementation. Therefore, the definition of terminology related to nuclear material is explored herein, within the highest-level legislation on the safeguards and physical protection. First the definition in Korean legislation is analyzed. Then, so as to suggest some improvements, other international efforts are examined and some case studies are conducted on other states which have similar level of nuclear technology and industry to Korea. Finally, a draft of definition on nuclear material in perspective of nuclear nonproliferation and security is suggested based on the analysis below. The recommendation showed the draft nuclear material definition in nuclear control. The text will facilitate the understanding of nuclear material in the context of nuclear nonproliferation and security. It might provide appropriate provision for future legislation related to nuclear nonproliferation and security. For effective safeguards and physical protection measures, nuclear material should be presented with in a consistent manner as shown in the case of United Kingdom. It will be much more helpful if further material engineering studies on each nuclear material are produced. Multi-dimensional approach is required for the studies on the degree of efforts to divert

  20. Definition of Nuclear Material in Aspects of Nuclear Nonproliferation and Security

    Energy Technology Data Exchange (ETDEWEB)

    Jeon, Ji Hye; Lee, Chan Suh [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

    2014-10-15

    Nuclear safety accidents directly affect human health but nuclear security incidents indirectly influence human, which demonstrates the reason why security receives less attention. However, it is acknowledged that nuclear terrorism is indeed one of the most dreadful threat humanity faces. As part of strengthening nuclear security as well as nonproliferation to response to the threat, we need a better understanding of the nuclear material which needs to be safe under the objective of nuclear security. In reality, practitioners implement safeguards and physical protection in compliance with the regulation text in domestic legislation. Thus, it is important to specify nuclear material clearly in law for effective implementation. Therefore, the definition of terminology related to nuclear material is explored herein, within the highest-level legislation on the safeguards and physical protection. First the definition in Korean legislation is analyzed. Then, so as to suggest some improvements, other international efforts are examined and some case studies are conducted on other states which have similar level of nuclear technology and industry to Korea. Finally, a draft of definition on nuclear material in perspective of nuclear nonproliferation and security is suggested based on the analysis below. The recommendation showed the draft nuclear material definition in nuclear control. The text will facilitate the understanding of nuclear material in the context of nuclear nonproliferation and security. It might provide appropriate provision for future legislation related to nuclear nonproliferation and security. For effective safeguards and physical protection measures, nuclear material should be presented with in a consistent manner as shown in the case of United Kingdom. It will be much more helpful if further material engineering studies on each nuclear material are produced. Multi-dimensional approach is required for the studies on the degree of efforts to divert

  1. Data quality objectives for moisture measurement in stabilized special nuclear material

    International Nuclear Information System (INIS)

    Weier, D.R.; Pulsipher, B.A.; Silvers, K.L.

    2000-01-01

    Data Quality Objectives methodology is applied to Loss-on-Ignition (LOI) moisture content testing for stabilized nuclear materials. This work was performed by Pacific Northwest National Laboratory in support of the Plutonium Finishing Plant (PFP)/Fluor Hanford, Inc. Historical results on LOI test results for two material types, oxide and sludge, are used to estimate within container variability. This variability estimate is then used in formulating the two recommended acceptance criteria for containers of material. The criteria which follow are proposed to replace the current criterion, which requires recycle if either of two container LOI measurements exceed 0.5 wt%, the DOE Standard 3013-99 threshold value. (1) The 95% upper confidence limit (UCL) for the true mean underlying moisture content in the container material should be less than 0.5 wt%. (2) The difference between the two LOI measurements per container should not exceed their expected 95th percentile relative to the estimated variability. Containers not meeting the first criterion, or those that generate in any negative LOI result, require material recycle. Containers not meeting the second criteria require review of the measurement results, potentially leading to resampling and retesting. Data from Los Alamos National Laboratory studies on moisture testing are obtained and analyzed. The performance of Supercritical Fluid Extraction (SFE), which will soon be implemented at the PFP, is described for several material types. This information will be used to establish initial acceptance criteria when SFE comes on line

  2. Induced-Fission Imaging of Nuclear Material

    International Nuclear Information System (INIS)

    Hausladen, Paul; Blackston, Matthew A.; Mullens, James Allen; McConchie, Seth M.; Mihalczo, John T.; Bingham, Philip R.; Ericson, Milton Nance; Fabris, Lorenzo

    2010-01-01

    This paper presents initial results from development of the induced-fission imaging technique, which can be used for the purpose of measuring or verifying the distribution of fissionable material in an unopened container. The technique is based on stimulating fissions in nuclear material with 14 MeV neutrons from an associated-particle deuterium-tritium (D-T) generator and counting the subsequent induced fast fission neutrons with an array of fast organic scintillation detectors. For each source neutron incident on the container, the neutron creation time and initial trajectory are known from detection of the associated alpha particle of the d + t → α + n reaction. Many induced fissions will lie along (or near) the interrogating neutron path, allowing an image of the spatial distribution of prompt induced fissions, and thereby fissionable material, to be constructed. A variety of induced-fission imaging measurements have been performed at Oak Ridge National Laboratory with a portable, low-dose D-T generator, including single-view radiographic measurements and three-dimensional tomographic measurements. Results from these measurements will be presented along with the neutron transmission images that have been performed simultaneously. This new capability may have applications to a number of areas in which there may be a need to confirm the presence or configuration of nuclear materials, such as nuclear material control and accountability, quality assurance, treaty confirmation, or homeland security applications.

  3. Combating illicit trafficking in nuclear and other radioactive material. Reference material

    International Nuclear Information System (INIS)

    2007-01-01

    This publication is intended for individuals and organizations that may be called upon to deal with the detection of and response to criminal or unauthorized acts involving nuclear or other radioactive material. It will also be useful for legislators, law enforcement agencies, government officials, technical experts, lawyers, diplomats and users of nuclear technology. This manual emphasizes the international initiatives for improving the security of nuclear and other radioactive material. However, it is recognized that effective measures for controlling the transfer of equipment, non-nuclear material, technology or information that may assist in the development of nuclear explosive devices, improvised nuclear devices (INDs) or other radiological dispersal devices (RDDs) are important elements of an effective nuclear security system. In addition, issues of personal integrity, inspection and investigative procedures are not discussed in this manual, all of which are essential elements for an effective overall security system. The manual considers a variety of elements that are recognized as being essential for dealing with incidents of criminal or unauthorized acts involving nuclear and other radioactive material. Depending on conditions in a specific State, including its legal and governmental infrastructure, some of the measures discussed will need to be adapted to suit that State's circumstances. However, much of the material can be applied directly in the context of other national programmes. This manual is divided into four main parts. Section 2 discusses the threat posed by criminal or unauthorized acts involving nuclear and other radioactive material, as well as the policy and legal bases underlying the international effort to restrain such activities. Sections 3 and 4 summarize the major international undertakings in the field. Sections 5-8 provide some basic technical information on radiation, radioactive material, the health consequences of radiation

  4. The century of nuclear materials

    Science.gov (United States)

    Mansur, Lou; Was, Gary S.; Zinkle, Steve; Petti, David; Ukai, Shigeharu

    2018-03-01

    In the spring of 1959 the well-read metallurgist would have noticed the first issue of an infant Journal, one dedicated to a unique and fast growing field of materials issues associated with nuclear energy systems. The periodical, Journal of Nuclear Materials (JNM), is now the leading publication in the field from which it takes its name, thriving beyond the rosiest expectations of its founders. The discipline is well into the second half-century. During that time much has been achieved in nuclear materials; the Journal provides the authoritative record of virtually all those accomplishments. These pages introduce the 500th volume, a significant measure in the world of publishing. The Editors reflect on the progress in the field and the role of this journal.

  5. International conference on security of material. Measures to prevent, intercept and respond to illicit uses of nuclear material and radioactive sources. Book of extended synopses

    International Nuclear Information System (INIS)

    2001-10-01

    The papers cover the subjects relating to the trafficking of highly enriched nuclear materials, less radioactive, radioactive materials, radiations sources, prevention of crime, capabilities of preventing smuggling, radiation detection devices that are or should be applied on borders. Different aspects of physical protection, security and safety of nuclear materials in a number of countries are discussed. A number of papers are devoted to detectors, and measuring methods

  6. International conference on security of material. Measures to prevent, intercept and respond to illicit uses of nuclear material and radioactive sources. Book of extended synopses

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-10-01

    The papers cover the subjects relating to the trafficking of highly enriched nuclear materials, less radioactive, radioactive materials, radiations sources, prevention of crime, capabilities of preventing smuggling, radiation detection devices that are or should be applied on borders. Different aspects of physical protection, security and safety of nuclear materials in a number of countries are discussed. A number of papers are devoted to detectors, and measuring methods.

  7. Determination of technical details concerning measures for transportation of nuclear fuel materials in the works or the enterprise

    International Nuclear Information System (INIS)

    1979-01-01

    The determination is defined under the regulations concerning the fabricating business of nuclear fuel materials, the regulation concerning installation and operation of test reactor, the regulations concerning the reprocessing business of spent fuel and the regulations concerning the uses of nuclear source materials. The notification determining technical details concerning measures for transportation of nuclear fuel materials is abolished. Measures for prevention of hazard designated by the Director General of Science and Technology Agency include such ones not to let radioactive materials easily fly about or leak in regular transport, not to let rain water easily penetrate or make each exterior side of a cubic load more than 10 centi-meters. The application for permission shall be filed for transportation of things highly difficult to be sealed in a vessel, listing name and address of the applicant, kind, quantity, form and nature of the load contaminated by nuclear fuel materials, date and route of transfer and measures taken for prevention of hazard in transport. Radiation doses of load and transporting apparatus are stipulated by the Director for an hour as 200 mili-rem on the surface of load, 10 mili-rem at the distance of 1 meter from the surface of load, and 200 mili-rem on the surface of the vehicle, etc. Dangerous things, signals and radiation dose of particular loads are specified respectively. (Okada, K.)

  8. Analysis of difficulties accounting and evaluating nuclear material of PWR fuel plant

    International Nuclear Information System (INIS)

    Zhang Min; Jue Ji; Liu Tianshu

    2013-01-01

    Background: Nuclear materials accountancy must be developed for nuclear facilities, which is required by regulatory in China. Currently, there are some unresolved problems for nuclear materials accountancy of bulk nuclear facilities. Purpose: The retention values and measurement errors are analyzed in nuclear materials accountancy of Power Water Reactor (PWR) fuel plant to meet the regulatory requirements. Methods: On the basis of nuclear material accounting and evaluation data of PWR fuel plant, a deep analysis research including ratio among random error variance, long-term systematic error variance, short-term systematic error variance and total error involving Material Unaccounted For (MUF) evaluation is developed by the retention value measure in equipment and pipeline. Results: In the equipment pipeline, the holdup estimation error and its total proportion are not more than 5% and 1.5%, respectively. And the holdup estimation can be regraded as a constant in the PWR nuclear material accountancy. Random error variance, long-term systematic error variance, short-term systematic error variance of overall measurement, and analytical and sampling methods are also obtained. A valuable reference is provided for nuclear material accountancy. Conclusion: In nuclear material accountancy, the retention value can be considered as a constant. The long-term systematic error is a main factor in all errors, especially in overall measurement error and sampling error: The long-term systematic errors of overall measurement and sampling are considered important in the PWR nuclear material accountancy. The proposals and measures are applied to the nuclear materials accountancy of PWR fuel plant, and the capacity of nuclear materials accountancy is improved. (authors)

  9. DA and NDA measurement of nuclear materials Mayak reprocessing plant

    International Nuclear Information System (INIS)

    Dzekun, E.G.; Lelyuk, G.A.; Sazhnov, V.K.

    1999-01-01

    Methods of nuclear material (NM) analysis and their quality assurance at the laboratory of RT-1 plant of PA Mayak are reviewed as applicable to the NM control and accounting system. The impact of analysis quality on the NM control and accounting system quality is analyzed. It has been shown that major component of the inventory difference for plutonium is caused by the errors of its measurement in the initial solution. The expedience of decreasing this error from 5 % to 1-1.5 % has been substantiated. Errors of plutonium detection on the other flows of NM at the facility prove to be acceptable for the NM control and accounting system. Accuracy of uranium concentration measurements proved to be satisfactory for all NM flows [ru

  10. Nuclear Forensic Science: Analysis of Nuclear Material Out of Regulatory Control

    Science.gov (United States)

    Kristo, Michael J.; Gaffney, Amy M.; Marks, Naomi; Knight, Kim; Cassata, William S.; Hutcheon, Ian D.

    2016-06-01

    Nuclear forensic science seeks to identify the origin of nuclear materials found outside regulatory control. It is increasingly recognized as an integral part of a robust nuclear security program. This review highlights areas of active, evolving research in nuclear forensics, with a focus on analytical techniques commonly employed in Earth and planetary sciences. Applications of nuclear forensics to uranium ore concentrates (UOCs) are discussed first. UOCs have become an attractive target for nuclear forensic researchers because of the richness in impurities compared to materials produced later in the fuel cycle. The development of chronometric methods for age dating nuclear materials is then discussed, with an emphasis on improvements in accuracy that have been gained from measurements of multiple radioisotopic systems. Finally, papers that report on casework are reviewed, to provide a window into current scientific practice.

  11. Analysis on the Decision Making on Nuclear Material Measurements for Safeguards Efficiency and Effectiveness on Research and Power Reactors

    International Nuclear Information System (INIS)

    Petit Wiringgalih; Basuki Wibowo

    2004-01-01

    This paper discusses three options in quantifying nuclear materials, ie. status quo, mobile unit measurement and centralised measurement. These three options are compared based on their safeguards effectiveness, timeline / efficiency, cost and safety aspects. Status quo measurement relies unverified estimation on nuclear materials, mobile unit measurement utilise NDA technique in order to obtain more accurate result while centralised measurement system transfers all measurements to another facility which posses more sophisticated equipment. Each of these three measurement options posesses relative advantages and disadvantages over the others. Status quo quantification is easy to perform but entails high inaccuracy. Mobile unit quantification is probably the best option, but it yields higher cost and radiation doses to workers. Centralised measurement facility is difficult to realise since the radioactive materials have to be coverted to their stable form. (author)

  12. The system of nuclear material control of Kazakhstan

    International Nuclear Information System (INIS)

    Yeligbayeva, G.Zh.

    2001-01-01

    Full text: The State system for nuclear material control consists of three integral components. The efficiency of each is to guarantee the non-proliferation regime in Kazakhstan. The components are the following: accounting, export and import control and physical protection of nuclear materials. First, the implementation of the goals of accounting and control bring into force, by the organization of the system for accounting and measurement of nuclear materials to determine present quantity. Organizing the accounting for nuclear material at facilities will ensure the efficiency of accountancy and reporting information. This defines the effectiveness of the state system for the accounting for the Kazakhstan's nuclear materials. Currently, Kazakhstan's nuclear material is fully safeguarded in designated secure locations. Kazakhstan has a nuclear power plant, 4 research reactors and a fuel fabrication plant. The governmental information system for nuclear materials control consist of two level: Governmental level - KAEA collects reports from facilities and prepares the reports for International Atomic Energy Agency, keeping of supporting documents and other necessary information, a data base of export and import, a data base of nuclear material inventory. Facility level - registration and processing information from key measurement points, formation the facility's nuclear materials accounting database. All facilities have computerized systems. Currently, all facilities are safeguarded under IAEA safeguarding standards, through IAEA inspections. Annually, IAEA verifies all nuclear materials at all Kazakhstan nuclear facilities. The government reporting system discloses the existence of all nuclear material and its transfer intended for interaction through the export control system and the nuclear control accounting system. Nuclear material export is regulated by the regulations of the Nuclear Export Control Law. The standard operating procedure is the primary means for

  13. Estimation methods for special nuclear materials holdup

    International Nuclear Information System (INIS)

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

    1984-01-01

    The potential value of statistical models for the estimation of residual inventories of special nuclear materials was examined using holdup data from processing facilities and through controlled experiments. Although the measurement of hidden inventories of special nuclear materials in large facilities is a challenging task, reliable estimates of these inventories can be developed through a combination of good measurements and the use of statistical models. 7 references, 5 figures

  14. The Physical Protection of Nuclear Material

    International Nuclear Information System (INIS)

    1993-09-01

    Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international cooperation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and materials, particularly when such materials are transported across national frontiers [es

  15. The Physical Protection of Nuclear Material

    International Nuclear Information System (INIS)

    1993-09-01

    Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international cooperation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and materials, particularly when such materials are transported across national frontiers [fr

  16. The Physical Protection of Nuclear Material

    International Nuclear Information System (INIS)

    1993-01-01

    Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international cooperation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and materials, particularly when such materials are transported across national frontiers

  17. The Physical Protection of Nuclear Material

    International Nuclear Information System (INIS)

    1993-09-01

    Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international cooperation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and materials, particularly when such materials are transported across national frontiers

  18. Measure of hydrogen concentration profile in materials by resonant nuclear reactions

    International Nuclear Information System (INIS)

    Livi, R.P.; Zawislak, F.C.; Acquadro, J.C.

    1986-01-01

    The technique for determining the profile of hydrogen concentration in proximities of the surface of materials, is presented. The preliminary measurements were done, using the Pelletron accelerator at Sao Paulo University (USP), in Brazil, for the resonant-nuclear reaction 1 H( 19 F, α γ) 16 O. By using this reaction the technique is sensitive for concentrations above 500 ppm, which could be reduced to 100 ppm through special shieldings and other techniques to reduce the background radiation. (M.C.K.) [pt

  19. Security of material: Preventing criminal activities involving nuclear and other radioactive materials

    International Nuclear Information System (INIS)

    Nilsson, A.

    2001-01-01

    The report emphasizes the need for national regulatory authorities to include in the regulatory systems, measures to control and protect nuclear materials from being used in illegal activities, as well as aspects of relevance for detecting and responding to illegal activities involving nuclear and other radioactive materials. The report will give an overview of the international treaties and agreements that underpin the establishment of a regulatory structure necessary for States to meet their non-proliferation policy and undertakings. Ongoing work to strengthen the protection of nuclear material and to detect and respond to illegal activities involving nuclear and other radioactive material will be included. The focus of the paper is on the need for standards and national regulation in the nuclear security area. (author)

  20. IAEA coordinated research project on improvement of technical measures to detect and respond to illicit trafficking of nuclear and other radioactive materials

    International Nuclear Information System (INIS)

    Abedin-Zadeh, R.; Abou-Zahra, A.; Weiss, B.

    2002-01-01

    Full text: Monitoring to detect the illicit trafficking of nuclear and other radioactive materials includes screening vehicles, cargo and individuals at borders to 1) detect smuggling of these materials; 2) locate, measure and characterize the source of radiation; and 3) fully characterize any confiscated material. Currently available instruments used for the field measurements are not optimized for this purpose and may not detect shielded plutonium and highly enriched uranium. Confiscated radioactive materials need to be characterized with macro- and microanalysis techniques to fully understand the significance of the material and to provide credible evidence in the event of prosecution of the traffickers. Although most States have national laboratories capable to determine the basic characteristics of such material, only a few member States have the sophisticated analytical capability necessary to perform proper forensics analysis. The coordinated research project on 'Improvement of Technical Measures to Detect and Respond to Illicit Trafficking of Nuclear and other Radioactive Materials' has been established to: Improve the detection capability and performance of hand-held and portable isotope measurement devices, including the technical and functional specifications for such devices; standardize procedures to examine suspicious packages and to assess the hazard of confiscated material; and develop recommendations and guidelines for establishing a system to provide nuclear forensics support to member States for the characterization of seized nuclear material. Related to the nuclear forensics support, it should be noted that with the inception of the Agency's nuclear security programme in 1995, the IAEA has offered the services of its laboratories in Seibersdorf and associated laboratories to assist States in analysing confiscated nuclear materials. Since 1993 the IAEA has received reports of over 300 cases of smuggling of nuclear and other radioactive materials

  1. Nuclear materials stewardship: Our enduring mission

    International Nuclear Information System (INIS)

    Isaacs, T.H.

    1998-01-01

    The US Department of Energy (DOE) and its predecessors have handled a remarkably wide variety of nuclear materials over the past 50 yr. Two fundamental changes have occurred that shape the current landscape regarding nuclear materials. If one recognizes the implications and opportunities, one sees that the stewardship of nuclear materials will be a fundamental and important job of the DOE for the foreseeable future. The first change--the breakup of the Soviet Union and the resulting end to the nuclear arms race--altered US objectives. Previously, the focus was on materials production, weapon design, nuclear testing, and stockpile enhancements. Now the attention is on dismantlement of weapons, excess special nuclear material inventories, accompanying increased concern over the protection afforded to such materials; new arms control measures; and importantly, maintenance of the safety and reliability of the remaining arsenal without testing. The second change was the raised consciousness and sense of responsibility for dealing with the environmental legacies of past nuclear arms programs. Recognition of the need to clean up radioactive contamination, manage the wastes, conduct current operations responsibly, and restore the environment have led to the establishment of what is now the largest program in the DOE. Two additional features add to the challenge and drive the need for recognition of nuclear materials stewardship as a fundamental, enduring, and compelling mission of the DOE. The first is the extraordinary time frames. No matter what the future of nuclear weapons and no matter what the future of nuclear power, the DOE will be responsible for most of the country's nuclear materials and wastes for generations. Even if the Yucca Mountain program is successful and on schedule, it will last more than 100 yr. Second, the use, management, and disposition of nuclear materials and wastes affect a variety of nationally important and diverse objectives, from national

  2. Fundamentals of materials accounting for nuclear safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Pillay, K.K.S. (comp.)

    1989-04-01

    Materials accounting is essential to providing the necessary assurance for verifying the effectiveness of a safeguards system. The use of measurements, analyses, records, and reports to maintain knowledge of the quantities of nuclear material present in a defined area of a facility and the use of physical inventories and materials balances to verify the presence of special nuclear materials are collectively known as materials accounting for nuclear safeguards. This manual, prepared as part of the resource materials for the Safeguards Technology Training Program of the US Department of Energy, addresses fundamental aspects of materials accounting, enriching and complementing them with the first-hand experiences of authors from varied disciplines. The topics range from highly technical subjects to site-specific system designs and policy discussions. This collection of papers is prepared by more than 25 professionals from the nuclear safeguards field. Representing research institutions, industries, and regulatory agencies, the authors create a unique resource for the annual course titled ''Materials Accounting for Nuclear Safeguards,'' which is offered at the Los Alamos National Laboratory.

  3. Use of Nuclear Material Accounting and Control for Nuclear Security Purposes at Facilities. Implementing Guide

    International Nuclear Information System (INIS)

    2015-01-01

    Nuclear material accounting and control (NMAC) works in a complementary fashion with the international safeguards programme and physical protection systems to help prevent, deter or detect the unauthorized acquisition and use of nuclear materials. These three methodologies are employed by Member States to defend against external threats, internal threats and both state actors and non-state actors. This publication offers guidance for implementing NMAC measures for nuclear security at the nuclear facility level. It focuses on measures to mitigate the risk posed by insider threats and describes elements of a programme that can be implemented at a nuclear facility in coordination with the physical protection system for the purpose of deterring and detecting unauthorized removal of nuclear material

  4. Device for separating, purifying and recovering nuclear fuel material, impurities and materials from impurity-containing nuclear fuel materials or nuclear fuel containing material

    International Nuclear Information System (INIS)

    Sato, Ryuichi; Kamei, Yoshinobu; Watanabe, Tsuneo; Tanaka, Shigeru.

    1988-01-01

    Purpose: To separate, purify and recover nuclear fuel materials, impurities and materials with no formation of liquid wastes. Constitution: Oxidizing atmosphere gases are introduced from both ends of a heating furnace. Vessels containing impurity-containing nuclear fuel substances or nuclear fuel substance-containing material are continuously disposed movably from one end to the other of the heating furnace. Then, impurity oxides or material oxides selectively evaporated from the impurity-containing nuclear fuel substances or nuclear fuel substance-containing materials are entrained in the oxidizing atmosphere gas and the gases are led out externally from a discharge port opened at the intermediate portion of the heating furnace, filters are disposed to the exit to solidify and capture the nuclear fuel substances and traps are disposed behind the filters to solidify and capture the oxides by spontaneous air cooling or water cooling. (Sekiya, K.)

  5. Nuclear material accounting handbook

    International Nuclear Information System (INIS)

    2008-01-01

    immediately following the entry into force of its safeguards agreement, including some other possible obligations, are described. This section is intended to sensitize the officials involved in establishing nuclear accounting systems, reporting to the IAEA and facilitating inspections to attend to such matters. Part 2.1 relates to obligations of the State regarding INFCIRC/153-type agreements. Part 2.2 refers to accounting and reporting of source material in a State relating to a safeguards agreement and additional protocol. Part 2.3 presents other State obligations relating to accounting and reporting under bilateral agreements with another State(s). Part 2.4 describes resulting actions in a State necessary for establishing the SSAC in a State. This part also compares nuclear material accountancy with financial accountancy and other control measures. Section 3 describes the activities related to nuclear material accounting implementation at State level. Section 4 focuses on the development of accounting and reporting aspects at facility level. Section 5 attends to various topics relating to quality management. The IAEA, in applying safeguards in a State, expects to receive high quality data (e.g. correct, complete, accurate, consistent, formatted, timely and transmitted through appropriate channels). Proposals on systems to ensure this are discussed. Finally, the various appendices are included, such as pro forma forms, examples and diagrams, and the lists of references and abbreviations that will be of value to users of the handbook

  6. Material control and accounting at Exxon Nuclear, I

    International Nuclear Information System (INIS)

    Schneider, R.A.

    1985-01-01

    The nuclear material control and accounting system at Exxon Nuclear will be described in detail. Subjects discussed will include: the basis of the MC and A system, the nuclear materials accounting systems (NMRS and NICS), physical inventory taking, IAEA inspection experience, safeguards organization, measurements and measurement control, MUF evaluation, accounting forms and reports and use of tamper-indicating seals. The general requirements for material accounting and control in this type of a bulk-handling facility are described. The way those requirements are met for the subject areas shown above is illustrated using a reference (Model Plant) version of the Exxon Nuclear plant The difference between the item-accounting procedures used at reactor facilities and the bulk-accounting procedures used at fuel fabrication facilities is discussed in detail

  7. 10 CFR 74.51 - Nuclear material control and accounting for strategic special nuclear material.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Nuclear material control and accounting for strategic special nuclear material. 74.51 Section 74.51 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Formula Quantities of Strategic Special Nuclear...

  8. Regulations concerning the fabricating business of nuclear fuel materials

    International Nuclear Information System (INIS)

    1978-01-01

    The Regulation is revised on the basis of ''The law for the regulations of nuclear source materials, nuclear fuel materials and reactors'' and the ''Provisions concerning the enterprises processing nuclear fuel materials'' in the Enforcement Ordinance for the Law, to enforce such provisions. This is the complete revision of the regulation of the same name in 1957. Terms are explained, such as exposure radiation dose, cumulative dose, control area, surrounding inspection area, persons engaged in works, radioactive wastes, area for incoming and outgoing of materials, fluctuation of stocks, batch, real stocks, effective value and main measuring points. For the applications for the permission of the enterprises processing nuclear fuel materials, the location of an enterprise, the construction of buildings and the construction of and the equipments for facilities of chemical processing, forming, coating, assembling, storage of nuclear fuel materials, disposal of radioactive wastes and radiation control must be written. Records shall be made and maintained for the periods specified on the inspection of processing facilities, nuclear fuel materials, radiation control, operation, maintainance, accidents of processing facilities and weather. Limit to entrance into the control area, measures for exposure radiation dose, patrol and inspection, operation of processing facilities, transport of materials, disposal of radioactive wastes, safety regulations are provided for. Reports to be filed by the persons engaging in the enterprises processing nuclear fuel materials are prescribed. (Okada, K.)

  9. Reference materials and measurement traceability

    International Nuclear Information System (INIS)

    Bingham, C.D.

    1980-01-01

    Nuclear materials safeguards within the U.S.A. are accomplished by the integration of activities involving physical protection, material control and material accountability. Material accountability requires both sound measurement technology and well-defined accounting procedures to provide final evidence that physical protection and materials control have achieved their purpose. 5 refs

  10. Concerning enactment of regulations on burying of waste of nuclear fuel material or waste contaminated with nuclear fuel material

    International Nuclear Information System (INIS)

    1988-01-01

    The Atomic Safety Commission of Japan, after examining a report submitted by the Science and Technology Agency concerning the enactment of regulations on burying of waste of nuclear fuel material or waste contaminated with nuclear fuel material, has approved the plan given in the report. Thus, laws and regulations concerning procedures for application for waste burying business, technical standards for implementation of waste burying operation, and measures to be taken for security should be established to ensure the following. Matters to be described in the application for the approval of such business and materials to be attached to the application should be stipulated. Technical standards concerning inspection of waste burying operation should be stipulated. Measures to be taken for the security of waste burying facilities and security concerning the transportation and disposal of nuclear fuel material should be stipulated. Matters to be specified in the security rules should be stipulated. Matters to be recorded by waste burying business operators, measures to be taken to overcome dangers and matters to be reported to the Science and Technology Agency should be stipulated. (Nogami, K.)

  11. A Uniform Framework of Global Nuclear Materials Management

    International Nuclear Information System (INIS)

    Dupree, S.A.; Mangan, D.L.; Sanders, T.L; Sellers, T.A.

    1999-01-01

    Global Nuclear Materials Management (GNMM) anticipates and supports a growing international recognition of the importance of uniform, effective management of civilian, excess defense, and nuclear weapons materials. We expect thereto be a continuing increase in both the number of international agreements and conventions on safety, security, and transparency of nuclear materials, and the number of U.S.-Russian agreements for the safety, protection, and transparency of weapons and excess defense materials. This inventory of agreements and conventions may soon expand into broad, mandatory, international programs that will include provisions for inspection, verification, and transparency, To meet such demand the community must build on the resources we have, including State agencies, the IAEA and regional organizations. By these measures we will meet the future expectations for monitoring and inspection of materials, maintenance of safety and security, and implementation of transparency measures

  12. A Uniform Framework of Global Nuclear Materials Management

    Energy Technology Data Exchange (ETDEWEB)

    Dupree, S.A.; Mangan, D.L.; Sanders, T.L; Sellers, T.A.

    1999-04-20

    Global Nuclear Materials Management (GNMM) anticipates and supports a growing international recognition of the importance of uniform, effective management of civilian, excess defense, and nuclear weapons materials. We expect thereto be a continuing increase in both the number of international agreements and conventions on safety, security, and transparency of nuclear materials, and the number of U.S.-Russian agreements for the safety, protection, and transparency of weapons and excess defense materials. This inventory of agreements and conventions may soon expand into broad, mandatory, international programs that will include provisions for inspection, verification, and transparency, To meet such demand the community must build on the resources we have, including State agencies, the IAEA and regional organizations. By these measures we will meet the future expectations for monitoring and inspection of materials, maintenance of safety and security, and implementation of transparency measures.

  13. Lower-energy neutron sources for increasing the sensitivity of nuclear gages for measuring the water content of bulk materials

    International Nuclear Information System (INIS)

    Bailey, S.M.

    1977-01-01

    The sensitivity of a gage using a nuclear source for measuring the water content of bulk materials, such as plastic concrete, is increased by use of a lithium or fluorine neutron nuclear source. 3 figures

  14. Thermodynamics of nuclear materials

    International Nuclear Information System (INIS)

    1979-01-01

    Full text: The science of chemical thermodynamics has substantially contributed to the understanding of the many problems encountered in nuclear and reactor technology. These problems include reaction of materials with their surroundings and chemical and physical changes of fuels. Modern reactor technology, by its very nature, has offered new fields of investigations for the scientists and engineers concerned with the design of nuclear fuel elements. Moreover, thermodynamics has been vital in predicting the behaviour of new materials for fission as well as fusion reactors. In this regard, the Symposium was organized to provide a mechanism for review and discussion of recent thermodynamic investigations of nuclear materials. The Symposium was held in the Juelich Nuclear Research Centre, at the invitation of the Government of the Federal Republic of Germany. The International Atomic Energy Agency has given much attention to the thermodynamics of nuclear materials, as is evidenced by its sponsorship of four international symposia in 1962, 1965, 1967, and 1974. The first three meetings were primarily concerned with the fundamental thermodynamics of nuclear materials; as with the 1974 meeting, this last Symposium was primarily aimed at the thermodynamic behaviour of nuclear materials in actual practice, i.e., applied thermodynamics. Many advances have been made since the 1974 meeting, both in fundamental and applied thermodynamics of nuclear materials, and this meeting provided opportunities for an exchange of new information on this topic. The Symposium dealt in part with the thermodynamic analysis of nuclear materials under conditions of high temperatures and a severe radiation environment. Several sessions were devoted to the thermodynamic studies of nuclear fuels and fission and fusion reactor materials under adverse conditions. These papers and ensuing discussions provided a better understanding of the chemical behaviour of fuels and materials under these

  15. Development of advanced materials and devices for nuclear radiation measurements

    International Nuclear Information System (INIS)

    Gadkari, S.C.

    2015-01-01

    Single crystals of technologically important materials are grown in the Crystal Technology Section of the Technical Physics Division, BARC. These crystals find applications as scintillators and dosimeters in nuclear radiation detection/measurements. Scintillator crystals of some advanced materials like cerium doped Gd 3 Ga 3 Al 2 O 12 , Lu 2 SiO 5 , YAIO 3 etc and some conventional materials such as Bi 4 Ge 3 O 12 , CsI:Tl, NaI:Tl, etc have been grown from melts using the Czochralski and Bridgman techniques. Portable gamma-ray spectrometers that work from a USB port of a laptop have been developed using the grown scintillator crystals. In recent years there has been a flurry of research activities on materials containing Li 6 , B 10 , etc that have large capture cross-sections for neutrons to develop solid state detectors for neutrons. For this purpose single crystals of cerium doped Li 6 Y(BO 3 ) 3 and silver doped Li 2 B 4 O 7 have been developed. Optical, thermo-luminescence, photo-luminescence and scintillation properties of these crystals have been investigated with a view to develop detectors and dosimeters. The Li 2 B 4 O 7 :Ag is a tissue equivalent material (Z eff = 7.3 close to 7.4 of tissue) useful in the personal and medical dosimetry applications. As the emission of Ag + lies in the UV region (267 nm), a customized TL measurement set-up has been developed using a solar blind PMT that enabled the measurement of very low doses below 5 μGy and linearity up to 100 Gy. Films of CsI:TI in the 10 nm to 3 μm thickness range were deposited on silicon substrates using the physical vapor deposition technique under vacuum conditions. The deposited films investigated using SEM and AFM revealed a columnar growth behavior with a preferential orientation along <200>. The growth of single crystals from melts, recent efforts in the development of detectors and results of experiments conducted to detect thermal neutrons are described. (author)

  16. Development programs of cutting-edge technologies for measurement and detection of nuclear material for safeguards and security

    International Nuclear Information System (INIS)

    Seya, Michio; Wakabayashi, Shuji; Naoi, Yosuke; Ohkubo, Michiaki; Senzaki, Masao

    2011-01-01

    The Integrated Support Center for Nuclear Nonproliferation and Nuclear Security ('ISCN', hereafter) of Japan Atomic Energy Agency (JAEA) has development programs of cutting-edge technologies for measurement and detection of nuclear materials for nuclear safeguards and security, under the sponsorship of Japanese government (MEXT: Ministry of Education, Culture, Sports, Science and Technology). ISCN started development programs of the following technologies this year. (1) NRF (Nuclear Resonance Fluorescence) NDA technology using laser Compton scattering (LCS) gamma-rays, (2) Alternative to 3 He neutron detection technology using inorganic solid scintillator. ISCN is also going to conduct a demonstration test of a spent fuel Pu-NDA system that is to be developed by LANL (Los Alamos National Laboratory) using very sophisticated neutron measurement technologies, under JAEA/USDOE cooperation agreement. This presentation shows the above programs of ISCN. (author)

  17. New technologies for monitoring nuclear materials

    International Nuclear Information System (INIS)

    Moran, B.W.

    1993-01-01

    This paper describes new technologies for monitoring the continued presence of nuclear materials that are being evaluated in Oak Ridge, Tennessee, to reduce the effort, cost, and employee exposures associated with conducting nuclear material inventories. These technologies also show promise for the international safeguarding of process systems and nuclear materials in storage, including spent fuels. The identified systems are based on innovative technologies that were not developed for safeguards applications. These advanced technologies include passive and active sensor systems based on optical materials, inexpensive solid-state radiation detectors, dimensional surface characterization, and digital color imagery. The passive sensor systems use specialized scintillator materials coupled to optical-fiber technologies that not only are capable of measuring radioactive emissions but also are capable of measuring or monitoring pressure, weight, temperature, and source location. Small, durable solid-state gamma-ray detection devices, whose components are estimated to cost less than $25 per unit, can be implemented in a variety of configurations and can be adapted to enhance existing monitoring systems. Variations in detector design have produced significantly different system capabilities. Dimensional surface characterization and digital color imaging are applications of developed technologies that are capable of motion detection, item surveillance, and unique identification of items

  18. Mobile Techniques for Rapid Detection of Concealed Nuclear Material

    International Nuclear Information System (INIS)

    Rosenstock, W.; Koeble, T.; Risse, M.; Berky, W.

    2015-01-01

    To prevent the diversion of nuclear material as well as illicit production, transport and use of nuclear material we investigated in mobile techniques to detect and identify such material in the field as early as possible. For that purpose we use a highly sensitive gamma measurement system installed in a car. It consists of two large volume plastic scintillators, one on each side of the car, each scintillator with 12 l active volume, and two extreme sensitive high purity Germanium detectors with 57 cm 2 crystal diameter, cooled electrically. The measured data are processed immediately with integrated, appropriate analysis software for direct assessment including material identification and classification within seconds. The software for the plastic scintillators can differentiate between natural and artificial radioactivity, thus giving a clear hint for the existence of unexpected material. In addition, the system is equipped with highly sensitive neutron detectors. We have performed numerous measurements by passing different radioactive and nuclear sources in relatively large distances with this measurement car. Even shielded as well as masked material was detected and identified in most of the cases. We will report on the measurements performed in the field (on an exercise area) and in the lab and discuss the capabilities of the system, especially with respect to timeliness and identification. This system will improve the nuclear verification capabilities also. (author)

  19. The law for the regulations of nuclear source materials, nuclear fuel materials and reactors

    International Nuclear Information System (INIS)

    1987-01-01

    General provisions specify the purpose of the Law and definitions of terms used in it. Provisions relating to control of business management for refining cover designation of business operation, requirements for designation, permission and report of alteration, report of commencement of business operation, revocation of designation, recording, and measures for wastes. Provisions relating to control of business management for processing cover permission of operation, requirements for permission, approval of design and construction plan, inspection of facilities, report of commencement of business management, measures for maintenance, suspension of use of facilities, responsible personnel for handling nuclear fuel, and permit, obligations, etc. of responsible personnel for handing nuclear fuel. Provisions relating to control of construction and operation of nuclear reactor cover permission of construction, permission concerning nuclear reactor mounted on foreign nuclear powered ships, requirements for permission, etc. Other articles stipulate provisions relating to control of business management for reprocessing, use of nuclear fuel substances, use of materials and substances covered by international regulations, designation of inspection organizations, and other rules. (Nogami, K.)

  20. Nuclear material control systems for nuclear power plants

    International Nuclear Information System (INIS)

    1975-06-01

    Paragraph 70.51(c) of 10 CFR Part 70 requires each licensee who is authorized to possess at any one time special nuclear material in a quantity exceeding one effective kilogram to establish, maintain, and follow written material control and accounting procedures that are sufficient to enable the licensee to account for the special nuclear material in his possession under license. While other paragraphs and sections of Part 70 provide specific requirements for nuclear material control systems for fuel cycle plants, such detailed requirements are not included for nuclear power reactors. This guide identifies elements acceptable to the NRC staff for a nuclear material control system for nuclear power reactors. (U.S.)

  1. CETAMA contribution to safeguards and nuclear forensic analysis based on nuclear reference materials

    International Nuclear Information System (INIS)

    Roudil, D.; Rigaux, C.; Rivier, C.; Hubinois, J.C.; Aufore, L.

    2012-01-01

    Measurement quality is crucial for the safety of nuclear facilities: nuclear reference materials (CRM) and interlaboratory programs (ILC), beyond the assessment of analytical measurement quality, play an important role. In the nuclear field, the CETAMA proposes suitable scientific and technical developments, in particular the preparation and certification of CRM used either as analytical standards or as reference samples for ILCs. The growing emphasis on nuclear forensic measurements will require some re-certification of old CRMs. But the future analytical challenges of meeting nuclear fuel cycle needs and of ensuring safeguard performance improvements will also concern the future CRMs. (authors)

  2. 10 CFR 74.41 - Nuclear material control and accounting for special nuclear material of moderate strategic...

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Nuclear material control and accounting for special nuclear material of moderate strategic significance. 74.41 Section 74.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Special Nuclear Material...

  3. Certified reference materials and reference methods for nuclear safeguards and security.

    Science.gov (United States)

    Jakopič, R; Sturm, M; Kraiem, M; Richter, S; Aregbe, Y

    2013-11-01

    Confidence in comparability and reliability of measurement results in nuclear material and environmental sample analysis are established via certified reference materials (CRMs), reference measurements, and inter-laboratory comparisons (ILCs). Increased needs for quality control tools in proliferation resistance, environmental sample analysis, development of measurement capabilities over the years and progress in modern analytical techniques are the main reasons for the development of new reference materials and reference methods for nuclear safeguards and security. The Institute for Reference Materials and Measurements (IRMM) prepares and certifices large quantities of the so-called "large-sized dried" (LSD) spikes for accurate measurement of the uranium and plutonium content in dissolved nuclear fuel solutions by isotope dilution mass spectrometry (IDMS) and also develops particle reference materials applied for the detection of nuclear signatures in environmental samples. IRMM is currently replacing some of its exhausted stocks of CRMs with new ones whose specifications are up-to-date and tailored for the demands of modern analytical techniques. Some of the existing materials will be re-measured to improve the uncertainties associated with their certified values, and to enable laboratories to reduce their combined measurement uncertainty. Safeguards involve the quantitative verification by independent measurements so that no nuclear material is diverted from its intended peaceful use. Safeguards authorities pay particular attention to plutonium and the uranium isotope (235)U, indicating the so-called 'enrichment', in nuclear material and in environmental samples. In addition to the verification of the major ratios, n((235)U)/n((238)U) and n((240)Pu)/n((239)Pu), the minor ratios of the less abundant uranium and plutonium isotopes contain valuable information about the origin and the 'history' of material used for commercial or possibly clandestine purposes, and

  4. Non-destructive measurement technologies for nuclear safeguards

    International Nuclear Information System (INIS)

    Gavron, A.

    1998-04-01

    There are three aspects that need to be in place in order to maintain a valid safeguards system: (1) Physical protection; guarding the access to nuclear materials using physical protection and surveillance. (2) Accounting systems; computer based accounting systems that provide the current location of nuclear materials, quantities, and the uncertainty in the assayed values. (3) Measurement systems; detectors, data acquisition systems and data analysis methods that provide accurate assays of nuclear material quantities for the accounting system. The authors expand on this third aspect, measurement systems, by discussing nondestructive assay (NDA) techniques. NDA is defined as the quantitative or qualitative determination of the kind and/or amount of nuclear material in an item without alteration or invasion of the item. This is contrasted with destructive analysis which is the process of taking small samples from the item in question, analyzing those samples by chemical analysis, destroying the original nature of the samples in the process (hence the term destructive), and applying the results to the entire item. Over the past 30 years, numerous techniques, using the atomic and nuclear properties of the actinides, have been developed for reliable, rapid, accurate, and tamper-proof NDA of nuclear materials. The authors distinguish between two types of measurements: the first involving the detection of spontaneously emitted radiation, produced by the natural radioactive decay processes; the second involving the detection of induced radiation, produced by irradiating the sample with an external radiation source

  5. Software for MUF evaluating in item nuclear material accounting

    International Nuclear Information System (INIS)

    Wang Dong; Zhang Quanhu; He Bin; Wang Hua; Yang Daojun

    2009-01-01

    Nuclear material accounting is a key measure for nuclear safeguard. Software for MUF evaluation in item nuclear material accounting was worked out in this paper. It is composed of several models, including input model, data processing model, data inquiring model, data print model, system setting model etc. It could be used to check the variance of the measurement and estimate the confidence interval according to the MUF value. To insure security of the data multi-user management function was applied in the software. (authors)

  6. HB-Line Material Control and Accountability Measurements at SRS

    International Nuclear Information System (INIS)

    Casella, V.R.

    2003-01-01

    Presently, HB-Line work at the Savannah River Site consists primarily of the stabilization and packaging of nuclear materials for storage and the characterization of materials for disposition in H-Area. In order to ensure compliance with Material Control and Accountability (MC and A) Regulations, accountability measurements are performed throughout the HB-Line processes. Accountability measurements are used to keep track of the nuclear material inventory by constantly updating the amount of material in the MBAs (Material Balance Area) and sub-MBAs. This is done by subtracting the amount of accountable material that is added to a process and by adding the amount of accountable material that is put back in storage. A Physical Inventory is taken and compared to the ''Book Value'' listed in the Nuclear Material Accounting System. The difference (BPID) in the Book Inventory minus the Physical Inventory of a sub-account for bulk material must agree within the measurement errors combined in quadrature to provide assurance that nuclear material is accounted for. This work provides an overview of HB-Line processes and accountability measurements. The Scrap Recovery Line and Neptunium-237/Plutonium-239 Oxide Line are described and sampling and analyses for Phase II are provided. Recommendations for improvements are provided to improve efficiency and cost effectiveness

  7. Absolute nuclear material assay using count distribution (LAMBDA) space

    Science.gov (United States)

    Prasad, Manoj K [Pleasanton, CA; Snyderman, Neal J [Berkeley, CA; Rowland, Mark S [Alamo, CA

    2012-06-05

    A method of absolute nuclear material assay of an unknown source comprising counting neutrons from the unknown source and providing an absolute nuclear material assay utilizing a model to optimally compare to the measured count distributions. In one embodiment, the step of providing an absolute nuclear material assay comprises utilizing a random sampling of analytically computed fission chain distributions to generate a continuous time-evolving sequence of event-counts by spreading the fission chain distribution in time.

  8. Nuclear material inventory estimation in a nuclear fuel reprocessing facility

    International Nuclear Information System (INIS)

    Bennett, J.E.; Beyerlein, A.L.

    1981-01-01

    A new approach in the application of modern system identification and estimation techniques is proposed to help nuclear reprocessing facilities meet the nuclear accountability requirement proposed by the International Atomic Energy Agency. The proposed identification and estimation method considers the material inventory in a portion of the chemical separations area of a reprocessing facility. The method addresses the nonlinear aspects of the problem, the time delay through the separation facility, and the lack of measurement access. The method utilizes only input-output measured data and knowledge of the uncertainties associated with the process and measured data. 14 refs

  9. Measurements Matter in Nuclear Safeguards & Security

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  10. The nuclear materials contraband

    International Nuclear Information System (INIS)

    Williams, P.; Woessner, P.

    1996-01-01

    Several seizures of nuclear materials carried by contraband have been achieved. Some countries or criminal organizations could manufacture atomic bombs and use them. This alarming situation is described into details. Only 40% of drugs are seized by the American police and probably less in western Europe. The nuclear materials market is smaller than the drugs'one but the customs has also less experience to intercept the uranium dispatch for instance more especially as the peddlers are well organized. A severe control of the international transports would certainly allow to seize a large part of nuclear contraband materials but some dangerous isotopes as uranium 235 or plutonium 239 are little radioactive and which prevents their detection by the Geiger-Mueller counters. In France, some regulations allow to control the materials used to manufacture the nuclear weapons, and diminish thus the risk of a nuclear materials contraband. (O.L.). 4 refs., 2 figs

  11. Management of Global Nuclear Materials for International Security

    International Nuclear Information System (INIS)

    Isaacs, T; Choi, J-S

    2003-01-01

    Nuclear materials were first used to end the World War II. They were produced and maintained during the cold war for global security reasons. In the succeeding 50 years since the Atoms for Peace Initiative, nuclear materials were produced and used in global civilian reactors and fuel cycles intended for peaceful purposes. The Nonproliferation Treaty (NPT) of 1970 established a framework for appropriate applications of both defense and civilian nuclear activities by nuclear weapons states and non-nuclear weapons states. As global inventories of nuclear materials continue to grow, in a diverse and dynamically changing manner, it is time to evaluate current and future trends and needed actions: what are the current circumstances, what has been done to date, what has worked and what hasn't? The aim is to identify mutually reinforcing programmatic directions, leading to global partnerships that measurably enhance international security. Essential elements are material protection, control and accountability (MPC and A) of separated nuclear materials, interim storage, and geologic repositories for all nuclear materials destined for final disposal. Cooperation among key partners, such as the MPC and A program between the U.S. and Russia for nuclear materials from dismantled weapons, is necessary for interim storage and final disposal of nuclear materials. Such cooperative partnerships can lead to a new nuclear regime where a complete fuel cycle service with fuel leasing and spent fuel take-back can be offered to reactor users. The service can effectively minimize or even eliminate the incentive or rationale for the user-countries to develop their indigenous enrichment and reprocessing technologies. International cooperation, supported by governments of key countries can be best to facilitate the forum for formation of such cooperative partnerships

  12. Nuclear material accounting software for Ukraine

    International Nuclear Information System (INIS)

    Doll, M.; Ewing, T.; Lindley, R.; McWilliams, C.; Roche, C.; Sakunov, I.; Walters, G.

    1999-01-01

    Among the needs identified during initial surveys of nuclear facilities in Ukraine was improved accounting software for reporting material inventories to the regulatory body. AIMAS (Automated Inventory/Material Accounting System) is a PC-based application written in Microsoft Access that was jointly designed by an US/Ukraine development team. The design is highly flexible and configurable, and supports a wide range of computing infrastructure needs and facility requirements including situations where networks are not available or reliable. AIMAS has both English and Russian-language options for displays and reports, and it operates under Windows 3.1, 95, or NT 4.0trademark. AIMAS functions include basic physical inventory tracking, transaction histories, reporting, and system administration functions (system configuration, security, data backup and recovery). Security measures include multilevel password access control, all transactions logged with the user identification, and system administration control. Interfaces to external modules provide nuclear fuel burn-up adjustment and barcode scanning capabilities for physical inventory taking. AIMAS has been installed at Kiev Institute of Nuclear Research (KINR), South Ukraine Nuclear Power Plant (SUNPP), Kharkov Institute of Physics and Technology (KIPT), Sevastopol Institute of Nuclear Energy and Industry (SINEI), and the Ministry of Environmental Protection and Nuclear Safety/Nuclear Regulatory Administration (MEPNS/NRA). Facility specialists are being trained to use the application to track material movement and report to the national regulatory authority

  13. Safeguards for nuclear material transparency monitoring

    International Nuclear Information System (INIS)

    MacArthur, D.A.; Wolford, J.K.

    1999-01-01

    The US and the Russian Federation are currently engaged in negotiating or implementing several nuclear arms and nuclear material control agreements. These involve placing nuclear material in specially designed containers within controlled facilities. Some of the agreements require the removal of nuclear components from stockpile weapons. These components are placed in steel containers that are then sealed and tagged. Current strategies for monitoring the agreements involve taking neutron and gamma radiation measurements of components in their containers to monitor the presence, mass, and composition of plutonium or highly enriched uranium, as well as other attributes that indicate the use of the material in a weapon. If accurate enough to be useful, these measurements will yield data containing information about the design of the weapon being monitored. In each case, the design data are considered sensitive by one or both parties to the agreement. To prevent the disclosure of this information in a bilateral or trilateral inspection scenario, so-called information barriers have evolved. These barriers combine hardware, software, and procedural safeguards to contain the sensitive data within a protected volume, presenting to the inspector only the processed results needed for verification. Interlocks and volatile memory guard against disclosure in case of failure. Implementing these safeguards requires innovation in radiation measurement instruments and data security. Demonstrating their reliability requires independent testing to uncover any flaws in design. This study discusses the general problem and gives a proposed solution for a high resolution gamma ray detection system. It uses historical examples to illustrate the evolution of other successful systems

  14. Problems and management of radioactive sources and measures against illicit trafficking of nuclear materials in Bulgaria

    International Nuclear Information System (INIS)

    Strezov, A.

    1998-01-01

    Illicit trafficking of nuclear materials continues to pose a danger to public health and safety and to nuclear non proliferation efforts. The majority of cases so far have involved only small amounts of fissile materials or mainly radioactive sources in Bulgaria. A proper scheme for analysis of seized nuclear materials will be developed based on existing equipment for NDA analysis of nuclear materials supplemented by new system through PHARE project assistance by EU experts. (author)

  15. The regulations concerning the uses of nuclear source materials

    International Nuclear Information System (INIS)

    1981-01-01

    This rule is established under the provisions of the law concerning the regulation of nuclear raw materials, nuclear fuel materials and nuclear reactors and the ordinance for the execution of this law, and to enforce them. Basic terms are defined, such as exposure radiation dose, cumulative dose, control area, surrounding monitoring area, worker and radioactive waste. Nuclear raw materials shall be used at the facilities for using them, and control areas and surrounding monitoring areas shall be set up. Cumulative dose and exposure radiation dose of workers shall not exceed the permissible quantities defined by the General Director of the Science and Technology Agency. Records shall be made in each works or enterprise on the accept, delivery and stock of each kind of nuclear raw materials, radiation control and the accidents in the facilities of using nuclear raw materials, and kept for specified periods, respectively. The users of nuclear raw materials shall present reports in each works or enterprise on the stock of these materials on July 30 and December 31, every year. They shall submit reports immediately to the Director General on the particular accidents concerning nuclear raw materials and their facilities and on the circumstances and the measures taken against such accidents within ten days. These reports shall be presented on internationally regulated raw materials too. (Okada, K.)

  16. Control of Nuclear Materials and Special Equipment (Nuclear Safety Regulations)

    International Nuclear Information System (INIS)

    Cizmek, A.; Prah, M.; Medakovic, S.; Ilijas, B.

    2008-01-01

    Based on Nuclear Safety Act (OG 173/03) the State Office for Nuclear Safety (SONS) in 2008 adopted beside Ordinance on performing nuclear activities (OG 74/06) and Ordinance on special conditions for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety (OG 74/06) the new Ordinance on the control of nuclear material and special equipment (OG 15/08). Ordinance on the control of nuclear material and special equipment lays down the list of nuclear materials and special equipment as well as of nuclear activities covered by the system of control of production of special equipment and non-nuclear material, the procedure for notifying the intention to and filing the application for a license to carry out nuclear activities, and the format and contents of the forms for doing so. This Ordinance also lays down the manner in which nuclear material records have to be kept, the procedure for notifying the State administration organization (regulatory body) responsible for nuclear safety by the nuclear material user, and the keeping of registers of nuclear activities, nuclear material and special equipment by the State administration organization (regulatory body) responsible for nuclear safety, as well as the form and content of official nuclear safety inspector identification card and badge.(author)

  17. Experience of air transport of nuclear fuel material as type A package

    International Nuclear Information System (INIS)

    Kawasaki, Masashi; Kageyama, Tomio; Suzuki, Toru

    2004-01-01

    Special law on nuclear disaster countermeasures (hereafter called as to nuclear disaster countermeasures low) that is domestic law for dealing with measures for nuclear disaster, was enforced in June, 2000. Therefore, nuclear enterprise was obliged to report accidents as required by nuclear disaster countermeasures law, besides meeting the technical requirement of existent transport regulation. For overseas procurement of plutonium reference materials that are needed for material accountability, A Type package must be transported by air. Therefore, concept of air transport of nuclear fuel materials according to the nuclear disaster countermeasures law was discussed, and the manual including measures against accident in air transport was prepared for the oversea procurement. In this presentation, the concept of air transport of A Type package containing nuclear fuel materials according to the nuclear disaster countermeasures law, and the experience of a transportation of plutonium solution from France are shown. (author)

  18. Physics and technology of nuclear materials

    International Nuclear Information System (INIS)

    Ursu, I.

    1985-01-01

    The subject is covered in chapters, entitled; elements of nuclear reactor physics; structure and properties of materials (including radiation effects); fuel materials (uranium, plutonium, thorium); structural materials (including - aluminium, zirconium, stainless steels, ferritic steels, magnesium alloys, neutron irradiation induced changes in the mechanical properties of structural materials); moderator materials (including - nuclear graphite, natural (light) water, heavy water, beryllium, metal hydrides); materials for reactor reactivity control; coolant materials; shielding materials; nuclear fuel elements; nuclear material recovery from irradiated fuel and recycling; quality control of nuclear materials; materials for fusion reactors (thermonuclear fusion reaction, physical processes in fusion reactors, fuel materials, materials for blanket and cooling system, structural materials, materials for magnetic devices, specific problems of material irradiation). (U.K.)

  19. 37. annual meeting of the Institute of Nuclear Materials Management

    International Nuclear Information System (INIS)

    Anon.

    1996-01-01

    The following subjects were covered in this meeting: waste management; nuclear materials management -- safety and health; international safeguards; measurement control and statistics for nuclear materials management; material control and accountability; packaging and transportation; nonproliferation and arms control; and physical protection. Separate papers were prepared for 74 items of this meeting

  20. Physical protection of nuclear materials and facilities in CEA

    International Nuclear Information System (INIS)

    Garnier-Gratia, M.-H.; Jorda, A.

    2001-01-01

    Full text: CEA (Commissariat a l'Energie Atomique), as nuclear operator, is responsible for the control and protection of their nuclear materials. Inside CEA, DCS (Central Security Division) is in charge of the security matters, DCS defines the CEA strategy in this field, especially in physical protection. The paper will present the physical protection strategy of CEA. DCS defines the rules and methods; the operators have to apply in order to fulfill the security objectives of CEA. CEA has to provide the regulatory authority with documents proving that it is in accordance with the requirements of the 25th July 1980 law and 12th May 1981 decree. It has to implement all the necessary means in order to achieve the results requested by the regulatory authority. All these arrangements are described in the 'license and control file'. This file should specify the facility safeguards and physical protection system. Accounting measures are also described. In this file, the petitioner has to justify its capacity for holding nuclear materials and for exercising authorized activities on them. So the organization and the installed means have to be described in this authorization file. For physical protection, containment, surveillance and physical protection measures are presented: Containment measures must prevent the unauthorized or unjustified movements of nuclear material in the framework of the authorized activities; Surveillance measures must guarantee the integrity of the containment, check that no material is exiting by an abnormal channel; Physical protection measures for the materials, the premises and the facilities are intended to protect them against malevolent actions by means of security systems. The Central Security Division has established guidelines to provide guidance to the nuclear materials holders in writing such files. Each holding unit has to establish a 'license and control file' and each CEA site establishes a 'site license and control file

  1. Fundamental Technology Development for Radiation Damage in Nuclear Materials

    International Nuclear Information System (INIS)

    Kwon, Sang Chul; Kwon, J. H.; Kim, E. S. and others

    2005-04-01

    This project was performed to achieve technologies for the evaluation of radiation effects at materials irradiated at HANARO and nuclear power plants, to establish measurement equipment and software for the analysis of radiation defects and to set up facilities for the measurements of radiation damage with non-destructive methods. Major targets were 1) establishment of hot laboratories and remote handling facilities/ technologies for the radioactive material tests, 2) irradiation test for the simulation of nuclear power plant environment and measurement/calculation of physical radiation damage, 3) evaluation and analysis of nano-scale radiation damage, 4) evaluation of radiation embrittlement with ultrasonic resonance spectrum measurement and electromagnetic measurement and 5) basic research of radiation embrittlement and radiation damage mechanism. Through the performance of 3 years, preliminary basics were established for the application research to evaluation of irradiated materials of present nuclear power plants and GEN-IV systems. Particularly the results of SANS, PAS and TEM analyses were the first output in Korea. And computer simulations of radiation damage were tried for the first time in Korea. The technologies will be developed for the design of GEN-IV material

  2. Regulations on nuclear materials control of the People's Republic of China

    International Nuclear Information System (INIS)

    1996-01-01

    The present 'Regulations on Nuclear Materials Control of the People's Republic of China' were promulgated by the State Council on June 15, 1987, which are enacted to ensure safe and lawful use of nuclear materials, to prevent theft, sabotage, lose, unlawful diversion and unlawful use, to protect the security of the State and the Public and to facilitate the development of nuclear undertakings. The nuclear materials controlled are: 1. Uranium-235 (materials and products); 2. Uranium-233 (material and products); 3. Plutonium-239 (materials and products); 4. tritium (materials and products); 5. lithium-6 (materials and products); 6. Other nuclear materials requiring control. The present regulations are not applicable to the control of uranium ore and its primary products. The control measures for nuclear products transferred to the armed forces shall be laid down by the national defence department

  3. Safeguards: Modelling of the Detection and Characterization of Nuclear Materials

    International Nuclear Information System (INIS)

    Enqvist, Andreas

    2010-01-01

    Nuclear safeguards is a collective term for the tools and methods needed to ensure nonproliferation and safety in connection to utilization of nuclear materials. It encompasses a variety of concepts from legislation to measurement equipment. The objective of this thesis is to present a number of research results related to nuclear materials control and accountability, especially the area of nondestructive assay. Physical aspects of nuclear materials are often the same as for materials encountered in everyday life. One special aspect though is that nuclear materials also emit radiation allowing them to be qualitatively and quantitatively measured without direct interaction with the material. For the successful assay of the material, the particle generation and detection needs to be well understood, and verified with measurements, simulations and models. Four topics of research are included in the thesis. First the generation and multiplication of neutrons and gamma rays in a fissile multiplying sample is treated. The formalism used enables investigation of the number of generated, absorbed and detected particles, offering understanding of the different processes involved. Secondly, the issue of relating the coincident detector signals, generated by both neutrons and gamma rays, to sample parameters is dealt with. Fission rate depends directly on the sample mass, while parameters such as neutron generation by alpha decay and neutron leakage multiplication are parameters that depend on the size, composition and geometry of the sample. Artificial neural networks are utilized to solve the inverse problem of finding sample characteristics from the measured rates of particle multiples. In the third part the interactions between neutrons and organic scintillation detectors are treated. The detector material consists of hydrogen and carbon, on which the neutrons scatter and transfer energy. The problem shares many characteristics with the area of neutron moderation found in

  4. A saddle-point for data verification and materials accountancy to control nuclear material

    International Nuclear Information System (INIS)

    Beedgen, R.

    1983-01-01

    Materials accountancy is one of the main elements in international safeguards to determine whether or not nuclear material has been diverted in nuclear plants. The inspector makes independent measurements to verify the plant-operator's data before closing the materials balance with the operator's data. All inspection statements are in principle probability statements because of random errors in measuring the material and verification on a random sampling basis. Statistical test procedures help the inspector to decide under this uncertainty. In this paper a statistical test procedure representing a saddle-point is presented that leads to the highest guaranteed detection probability taking all concealing strategies into account. There are arguments favoring a separate statistical evaluation of data verification and materials accountancy. Following these considerations, a bivariate test procedure is explained that evaluates verification and accountancy separately. (orig.) [de

  5. Development of nuclear materials accounting for international safeguards

    International Nuclear Information System (INIS)

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

    1991-01-01

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

  6. Establishment of ultra trace nuclear material analysis system

    International Nuclear Information System (INIS)

    Song, Kyuseok; Jee, Kwangyong; Lee, Changheon

    2012-05-01

    Highly accurate and precise analysis of ultra trace nuclear materials contained in swipe samples and environmental samples is required to improve the national nuclear transparency and the international nuclear security. The objectives of the first stage of this project are to develop the techniques for bulk analysis of environmental samples and the elemental techniques for particle analysis using FT-TIMS. To accomplish the objectives, state-of-the-art analytical instruments were set up followed by the development of the techniques for screening of nuclear materials, chemical treatement, particle handling, isotopic measurements using TIMS and ICP-MS, and fabrication of uranium microparticles. The verifications of the developed techniques were carried out by measurement of reference materials, and by participation to interlaboratory comparison programs. In additon, the establishement of a quality management system and the performance of the analysis of QC samples for IAEA-NWAL qualification were carried out to obtain the international accreditation for the related analytical system. In this report, the results of research and developments, and the achievements to obtain the international accreditation were summarized

  7. Global nuclear material control model

    International Nuclear Information System (INIS)

    Dreicer, J.S.; Rutherford, D.A.

    1996-01-01

    The nuclear danger can be reduced by a system for global management, protection, control, and accounting as part of a disposition program for special nuclear materials. The development of an international fissile material management and control regime requires conceptual research supported by an analytical and modeling tool that treats the nuclear fuel cycle as a complete system. Such a tool must represent the fundamental data, information, and capabilities of the fuel cycle including an assessment of the global distribution of military and civilian fissile material inventories, a representation of the proliferation pertinent physical processes, and a framework supportive of national or international perspective. They have developed a prototype global nuclear material management and control systems analysis capability, the Global Nuclear Material Control (GNMC) model. The GNMC model establishes the framework for evaluating the global production, disposition, and safeguards and security requirements for fissile nuclear material

  8. Technology development for nuclear material accountability

    International Nuclear Information System (INIS)

    Hong, Jong Sook; Lee, Byung Doo; Cha, Hong Ryul; Choi, Hyoung Nai; Park, Ho Joon

    1991-03-01

    Using Segmented Gamma Scanning(SGS) System and coaxical Ge detector, the amounts of uranium in 55 gallon waste drums mixed with low density matrix material were determined by segmented gamma-scanning method. Various factors that influence sample measurement were identified as attenuation effects against sample container and matrix material counting loss effect by dead time and signal pile-up and radial and axial non-uniformity effects of sample. External transmission source, Yb-169, was used to correct gamma-ray attenuation by matrix material. The measure deviation caused by non-uniform distribution in the drum was minimized by rotating and dividing the drum. To calibrate the measurement system, calibration sources were prepared in the range of 50g, 100g, 300g, and 500g of U0 2 powder which let it stick to thin gummed papers and mix with other matrix materials such as papers, vinyl sheets, pieces of rubber gloves in 4 each drum. Under the calibrated assay system the uncertainty of measured amounts of UO 2 powder approached about 10% of absolute value at 1σ and a normal flow of waste stream can be maintained at least one drum per hour. On the other hand, in an effort to ease the nuclear material accounting for and control the flow of nuclear material in CANDU Fuel Fabrication Facility was analyzed to develope a model computer network interfaced with hardwares, structual design of network, computer operating system, and hardware set-up were studied to draw out the most practical network system. (Author)

  9. System to detect nuclear materials by active neutron method

    International Nuclear Information System (INIS)

    Koroev, M.; Korolev, Yu.; Lopatin, Yu.; Filonov, V.

    1999-01-01

    The report presents the results of the development of the system to detect nuclear materials by active neutron method measuring delayed neutrons. As the neutron source the neutron generator was used. The neutron generator was controlled by the system. The detectors were developed on the base of the helium-3 counters. Each detector consist of 6 counters. Using a number of such detectors it is possible to verify materials stored in different geometry. There is an spectrometric scintillator detector in the system which gives an additional functional ability to the system. The system could be used to estimate the nuclear materials in waste, to detect the unauthorized transfer of the nuclear materials, to estimate the material in tubes [ru

  10. The nuclear materials control system: Safeguards - circa 1957

    International Nuclear Information System (INIS)

    Thomas, C.C. Jr.

    1992-01-01

    In the late 1950s, the Westinghouse Electric Corporation undertook a nuclear materials control study for the Division of International Affairs of the US Atomic Energy Commission (AEC). The objective of the study was to develop a Nuclear Materials Control System (NMCS) that could be used under the US bilateral agreements or by the International Atomic Energy Agency. Phase I was a system study to determine the requirements for an NMCS for an assumed nuclear fuel complex. This paper summarizes aspects of Phase I studies addressing facility types, measurement points, and instrumentation needs and Phase II studies covering chemistry/chemical engineering, nuclear, special devices, and security devices and techniques. 1 fig

  11. Physics and technology of nuclear materials

    CERN Document Server

    Ursu, Ioan

    2015-01-01

    Physics and Technology of Nuclear Materials presents basic information regarding the structure, properties, processing methods, and response to irradiation of the key materials that fission and fusion nuclear reactors have to rely upon. Organized into 12 chapters, this book begins with selectively several fundamentals of nuclear physics. Subsequent chapters focus on the nuclear materials science; nuclear fuel; structural materials; moderator materials employed to """"slow down"""" fission neutrons; and neutron highly absorbent materials that serve in reactor's power control. Other chapters exp

  12. Solid state nuclear magnetic resonance: investigating the spins of nuclear related materials

    International Nuclear Information System (INIS)

    Charpentier, Th.

    2007-10-01

    The author reviews his successive research works: his research thesis work on the Multiple Quantum Magic Angle Spinning (MQMAS) which is a quadric-polar nucleus multi-quanta correlation spectroscopy method, the modelling of NMR spectra of disordered materials, the application to materials of interest for the nuclear industry (notably the glasses used for nuclear waste containment). He presents the various research projects in which he is involved: storing glasses, nuclear magnetic resonance in paramagnetism, solid hydrogen storing matrices, methodological and instrument developments in high magnetic field and high resolution solid NMR, long range distance measurement by solid state Tritium NMR (observing the structure and dynamics of biological complex systems at work)

  13. Material control in nuclear fuel fabrication facilities. Part II. Accountability, instrumentation and measurement techniques in fuel fabrication facilities

    International Nuclear Information System (INIS)

    Borgonovi, G.M.; McCartin, T.J.; McDaniel, T.; Miller, C.L.; Nguyen, T.

    1978-01-01

    This report describes the measurement techniques, the instrumentation, and the procedures used in accountability and control of nuclear materials, as they apply to fuel fabrication facilities. A general discussion is given of instrumentation and measurement techniques which are presently used being considered for fuel fabrication facilities. Those aspects which are most significant from the point of view of satisfying regulatory constraints have been emphasized. Sensors and measurement devices have been discussed, together with their interfacing into a computerized system designed to permit real-time data collection and analysis. Estimates of accuracy and precision of measurement techniques have been given, and, where applicable, estimates of associated costs have been presented. A general description of material control and accounting is also included. In this section, the general principles of nuclear material accounting have been reviewed first (closure of material balance). After a discussion of the most current techniques used to calculate the limit of error on inventory difference, a number of advanced statistical techniques are reviewed. The rest of the section deals with some regulatory aspects of data collection and analysis, for accountability purposes, and with the overall effectiveness of accountability in detecting diversion attempts in fuel fabrication facilities. A specific example of application of the accountability methods to a model fuel fabrication facility is given. The effect of random and systematic errors on the total material uncertainty has been discussed, together with the effect on uncertainty of the length of the accounting period

  14. Material control in nuclear fuel fabrication facilities. Part II. Accountability, instrumentation and measurement techniques in fuel fabrication facilities

    Energy Technology Data Exchange (ETDEWEB)

    Borgonovi, G.M.; McCartin, T.J.; McDaniel, T.; Miller, C.L.; Nguyen, T.

    1978-01-01

    This report describes the measurement techniques, the instrumentation, and the procedures used in accountability and control of nuclear materials, as they apply to fuel fabrication facilities. A general discussion is given of instrumentation and measurement techniques which are presently used being considered for fuel fabrication facilities. Those aspects which are most significant from the point of view of satisfying regulatory constraints have been emphasized. Sensors and measurement devices have been discussed, together with their interfacing into a computerized system designed to permit real-time data collection and analysis. Estimates of accuracy and precision of measurement techniques have been given, and, where applicable, estimates of associated costs have been presented. A general description of material control and accounting is also included. In this section, the general principles of nuclear material accounting have been reviewed first (closure of material balance). After a discussion of the most current techniques used to calculate the limit of error on inventory difference, a number of advanced statistical techniques are reviewed. The rest of the section deals with some regulatory aspects of data collection and analysis, for accountability purposes, and with the overall effectiveness of accountability in detecting diversion attempts in fuel fabrication facilities. A specific example of application of the accountability methods to a model fuel fabrication facility is given. The effect of random and systematic errors on the total material uncertainty has been discussed, together with the effect on uncertainty of the length of the accounting period.

  15. Characteristics of X-ray fluorescence of nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Park, Seunghoon; Kwak, Sung-Woo; Shin, Jung-Ki; Park, Uk-Rayng; Jung, Heejun [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

    2015-10-15

    LED is a technique of determination of uranium concentration as a continuous X-ray energy beams transmit a uranium liquid sample for safeguards. Compared to K-edge densitometer, due to relatively lower energy (L-edge energy is 17.17 keV) of Uranium L series energy than K-series energy, L-edge densitometer does not require high purity germanium detector with liquid nitride cooling. Therefore, the Ledge densitometer is appropriate for portable equipment for on-site nuclear material inspection and safeguards at facility sites. XRF combined with LED is a technique of finding of nuclear materials from reflected characteristic X-ray photons. In this study, characteristics of XRF of nuclear materials are simulated Monte Carlo method (Geant4) for feasibility of the system for determination of concentration of nuclear species. The analysis method of uranium concentration or minor actinides is applied using combination of linear extrapolation from jump of L-edge of sample and ratio between uranium and minor actinide from XRF measurement. In this study, The XRF ch aracteristics was simulated from Monte Carlo method. The peaks were obtained from nuclear material mixture. The estimated nuclear material concentration is low due to the volume effect of the sample. The correction factor or minimization of the effect is required.

  16. Uncovering Special Nuclear Materials by Low-energy Nuclear Reaction Imaging.

    Science.gov (United States)

    Rose, P B; Erickson, A S; Mayer, M; Nattress, J; Jovanovic, I

    2016-04-18

    Weapons-grade uranium and plutonium could be used as nuclear explosives with extreme destructive potential. The problem of their detection, especially in standard cargo containers during transit, has been described as "searching for a needle in a haystack" because of the inherently low rate of spontaneous emission of characteristic penetrating radiation and the ease of its shielding. Currently, the only practical approach for uncovering well-shielded special nuclear materials is by use of active interrogation using an external radiation source. However, the similarity of these materials to shielding and the required radiation doses that may exceed regulatory limits prevent this method from being widely used in practice. We introduce a low-dose active detection technique, referred to as low-energy nuclear reaction imaging, which exploits the physics of interactions of multi-MeV monoenergetic photons and neutrons to simultaneously measure the material's areal density and effective atomic number, while confirming the presence of fissionable materials by observing the beta-delayed neutron emission. For the first time, we demonstrate identification and imaging of uranium with this novel technique using a simple yet robust source, setting the stage for its wide adoption in security applications.

  17. Determination of internationally controlled materials according to provisions of the law for the regulations of nuclear source materials, nuclear fuel materials and reactors

    International Nuclear Information System (INIS)

    1984-01-01

    The internationally controlled materials determined according to the law for nuclear source materials, etc. are the following: nuclear source materials, nuclear fuel materials, moderating materials, facilities including reactors, etc. sold, transferred, etc. to Japan according to the agreements for peaceful uses of atomic energy between Japan, and the United States, the United Kingdom, Canada, Australia and France by the respective governments and those organs under them; nuclear fuel materials resulting from usage of the above sold and transferred materials, facilities; nuclear fuel materials sold to Japan according to agreements set by the International Atomic Energy Agency; nuclear fuel materials involved with the safeguards in nuclear weapons non-proliferation treaty with IAEA. (Mori, K.)

  18. An accountancy system for nuclear materials control in research centres

    International Nuclear Information System (INIS)

    Buttler, R.; Bueker, H.; Vallee, J.

    1979-01-01

    The Nuclear Accountancy and Control System (NACS) was developed at KFA Juelich in accordance with the requirements of the Non-Proliferation Treaty. The main features are (1) recording of nuclear material in inventory items. These are combined to form batches wherever suitable; (2) extrapolation of accounting data as a replacement for detailed measurement of inventory items data. Recording and control of nuclear material are carried out on two levels with access to a common data bank. The lower level deals with nuclear materials handling plus internal management while on the upper level there is a central control point which is responsible for nuclear safeguarding within the entire research centre. By keeping the organizational and technical infrastructure it was possible to develop a system which is both economical and operator-oriented. In this system the emphasis of nuclear safeguarding is placed on the acquisition of the nuclear material inventory. As much consideration has been given to the interests of the various operational levels and organizational units as to internal and national regulations. Since it is part of the safeguarding and control system, access to the NACS must be restricted to a limited number of users only. Furthermore, it must include facilities for manual control in the form of records. Authorization for access must correspond with the various tasks of different user groups. All necessary data are acquired decentrally in the organizational units and entered via a terminal. It is available to the user groups on both levels through a central data bank. To meet all requirements, the NACS has been designed as an integrated, computer-assisted information system for the automated processing of extensive and multi-level nuclear materials data. As part of the preventive measures entailed with nuclear safeguarding, the accountancy system enables the operator of a nuclear plant to furnish proof of non-diversion of nuclear material. (author)

  19. Joint ANSI-INMM 8.1: Nuclear Regulatory Commission study of uranium hexafluoride cylinder material accountability bulk measurements

    International Nuclear Information System (INIS)

    Pontius, P.E.; Doher, L.W.

    1977-01-01

    This paper reports the progress to date in a demonstration of the procedures in ANSI N15.18-1975, ''Mass Calibration Techniques for Nuclear Material Control,'' sponsored and funded by the Nuclear Regulatory Commission (NRC). The philosophy of mass measurement as a production process, as promulgated in ANSI N15.18-1975, is reviewed. Special emphasis is placed on the use of artifact Reference Mass Standards (RMS) as references for uranium hexafluoride (UF 6 ) calibration and bulk measurement processes. The history of the creation of the artifact concept and its adoption by ANSI N15.18-1975 and the Nuclear Regulatory Commission is narrated. The program now under way is specifically described; including descriptions of the RMS, their calibration, and the assignment of uncertainties to them by the National Bureau of Standards (NBS). Instrument tests, in-house standards (IHS), and assignment of values relative to the RMS-NBS values at nuclear facilities which measure UF 6 cylinders are described. Comparisons and the data base are detailed to provide realistic measurement process parameters associated with accountable transfer of UF 6 . The as yet uncompleted part of the demonstration is described, that is, to further close the measurement loop by verification both between and within facilities

  20. Croatian National System of Nuclear Materials Control

    International Nuclear Information System (INIS)

    Biscan, R.

    1998-01-01

    In the process of economic and technological development of Croatia by using or introducing nuclear power or in the case of international co-operation in the field of peaceful nuclear activities, including international exchange of nuclear material, Croatia should establish and implement National System of Nuclear Materials Control. Croatian National System of accounting for and control of all nuclear material will be subjected to safeguards under requirements of Agreement and Additional Protocol between the Republic of Croatia and the International Atomic Energy Agency (IAEA) for the Application of Safeguards in Connection with the Treaty on the Non-Proliferation of Nuclear Weapons (NPT). The decision by NPT parties at the 1995 NPT Review and Extension Conference to endorse the Fullscope IAEA Safeguards Standard (FSS) as a necessary precondition of nuclear supply means that states are obliged to ensure that the recipient country has a FSS agreement in place before any nuclear transfer can take place (Ref. 1). The FSS standard of nuclear supply is a central element of the Nuclear Suppliers Group (NSG) Guidelines which the NSG adopted in 1992 and should be applied to members and non-members of the NSG. The FSS standard of nuclear supply in general allows for NPT parties or countries which have undertaken the same obligations through other treaty arrangements, to receive favourable treatment in nuclear supply arrangements. However, the Iraqi experience demonstrate that trade in nuclear and dual-use items, if not properly monitored, can contribute to a nuclear weapons program in countries acting contrary to their non-proliferation obligation. Multilateral nuclear export control mechanisms, including the FSS supply standard, provide the basis for co-ordination and standardisation of export control measures. (author)

  1. Professional Nuclear Materials Management

    International Nuclear Information System (INIS)

    Forcella, A.A.; O'Leary, W.J.

    1966-01-01

    This paper describes the scope of nuclear materials management for a typical power reactor in the United States of America. Since this power reactor is financed by private capital, one of the principal obligations of the reactor operator is to ensure that the investment is protected and will furnish an adequate financial return. Because of the high intrinsic value of nuclear materials, appropriate security and accountability must be continually exercised to minimize losses beyond security and accountability for the nuclear materials. Intelligent forethought and planning must be employed to ensure that additional capital is not lost as avoidable additional costs or loss of revenue in a number of areas. The nuclear materials manager must therefore provide in advance against the following contingencies and maintain constant control or liaison against deviations from planning during (a) pre-reactor acquisition of fuel and fuel elements, (b) in-reactor utilization of the fuel elements, and (c) post-reactor recovery of fuel values. During pre-reactor planning and operations, it is important that the fuel element be designed for economy in manufacture, handling, shipping, and replaceability. The time schedule for manufacturing operations must minimize losses of revenue from unproductive dead storage of high cost materials. For in-reactor operations, the maximum achievable burn-up of the fissionable material must be obtained by means of appropriate fuel rearrangement schemes. Concurrently the unproductive down-time of the reactor for fuel rearrangement, inspections, and the like must be minimized. In the post-reactor period, when the fuel has reached a predetermined depletion of fissionable material, the nuclear materials manager must provide for the most economical reprocessing and recovery of fissionable values and by-products. Nuclear materials management is consequently an essential factor in achieving competitive fuel cycle and unit energy costs with power reactors

  2. A measurement evaluation program to support nuclear material control and accountability measurements in Brazilian laboratories

    International Nuclear Information System (INIS)

    Dias, Fabio C.; Mason, Peter

    2013-01-01

    A measurement evaluation program (MEP) is one of a number of valuable tools that analytical chemists can use to ensure that the data produced in the laboratory are fit for their intended purpose and consistent with expected performance values at a given time. As such, participation in a MEP is an important indicator of the quality of analytical data, and is recognized as such by independent regulatory and/or accreditation bodies. With the intent to implement such a program in Brazil, in November 2012 the Nuclear Energy Commission of Brazil (CNEN), with support from the Department of Energy of the United States' (US-DOE International Safeguards and Engagement Program), decided to initiate a technical cooperation project aiming at organizing a Safeguards Measurement Evaluation Program (SMEP) for Brazilian facilities. The project, entitled Action Sheet 23, was formalized under the terms of the Agreement between the US-DOE and the CNEN concerning research and development in nuclear material control, accountancy, verification, physical protection, and advanced containment and surveillance technologies for International Safeguards Applications. The work, jointly performed by the CNEN's Safeguards Laboratory (LASAL) and the New Brunswick Laboratory (NBL), has the objective to strengthen the traceability of accountability measurements and ensure adequate quality of safeguards measurements for facilities within Brazil, utilizing test samples characterized and provided by NBL. Recommendations to participants included measurement frequency, number of results per sample and format for reporting results using ISO methods for calculating and expressing measurement uncertainties. In this paper, we discuss the main steps taken by CNEN and NBL aiming at implementing such a program and the expected results, in particular the impact of uncertainty estimation on the evaluation of performance of each participant laboratory. The program is considered by Brazilian safeguards authorities

  3. A measurement evaluation program to support nuclear material control and accountability measurements in Brazilian laboratories

    Energy Technology Data Exchange (ETDEWEB)

    Dias, Fabio C., E-mail: fabio@ird.gov.br [Comissao Nacional de Energia Nuclear (CNEN-RJ), Rio de Janeiro, RJ (Brazil); Mason, Peter, E-mail: peter.mason@ch.doe.gov [New Brunswick Laboratory (DOE/NBL), Argonne, IL (United States)

    2013-07-01

    A measurement evaluation program (MEP) is one of a number of valuable tools that analytical chemists can use to ensure that the data produced in the laboratory are fit for their intended purpose and consistent with expected performance values at a given time. As such, participation in a MEP is an important indicator of the quality of analytical data, and is recognized as such by independent regulatory and/or accreditation bodies. With the intent to implement such a program in Brazil, in November 2012 the Nuclear Energy Commission of Brazil (CNEN), with support from the Department of Energy of the United States' (US-DOE International Safeguards and Engagement Program), decided to initiate a technical cooperation project aiming at organizing a Safeguards Measurement Evaluation Program (SMEP) for Brazilian facilities. The project, entitled Action Sheet 23, was formalized under the terms of the Agreement between the US-DOE and the CNEN concerning research and development in nuclear material control, accountancy, verification, physical protection, and advanced containment and surveillance technologies for International Safeguards Applications. The work, jointly performed by the CNEN's Safeguards Laboratory (LASAL) and the New Brunswick Laboratory (NBL), has the objective to strengthen the traceability of accountability measurements and ensure adequate quality of safeguards measurements for facilities within Brazil, utilizing test samples characterized and provided by NBL. Recommendations to participants included measurement frequency, number of results per sample and format for reporting results using ISO methods for calculating and expressing measurement uncertainties. In this paper, we discuss the main steps taken by CNEN and NBL aiming at implementing such a program and the expected results, in particular the impact of uncertainty estimation on the evaluation of performance of each participant laboratory. The program is considered by Brazilian safeguards

  4. The regulations concerning the uses of nuclear fuel materials

    International Nuclear Information System (INIS)

    1978-01-01

    The Regulations are established on the basis of ''The law for the regulations of nuclear source materials, nuclear fuel materials and reactors'' and the ''Provisions concerning the usage of nuclear fuel materials'' in the Enforcement Ordinance of the Law, to enforce such provisions. Terms are explained, such as exposure radiation dose, cumulative dose, control area, surrounding inspection area, persons engaging in works, area for incoming and outgoing of materials, batch, real stocks, effective value and main measuring points. In the applications for the permission to use nuclear fuel materials, the expected period and quantity of usage of each kind of such materials and the other party and the method of selling, lending and returning spent fuel or the process of disposal of such fuel must be written. Explanations concerning the technical ability required for the usage of nuclear fuel materials shall be attached to the applications. Applications shall be filed for the inspection of facilities for use, in which the name and the address of the applicant, the name and the address of the factory or the establishment, the range of the facilities for use, the maximum quantity of nuclear fuel materials to be used or stocked, and the date, the place and the kind of the expected inspection are written. Prescriptions cover the records to be held, safety regulations, the technical standards for usage, the disposal, transport and storage of nuclear fuel materials and the reports to be filed. (Okada, K.)

  5. Nuclear materials management storage study

    International Nuclear Information System (INIS)

    Becker, G.W. Jr.

    1994-02-01

    The Office of Weapons and Materials Planning (DP-27) requested the Planning Support Group (PSG) at the Savannah River Site to help coordinate a Departmental complex-wide nuclear materials storage study. This study will support the development of management strategies and plans until Defense Programs' Complex 21 is operational by DOE organizations that have direct interest/concerns about or responsibilities for nuclear material storage. They include the Materials Planning Division (DP-273) of DP-27, the Office of the Deputy Assistant Secretary for Facilities (DP-60), the Office of Weapons Complex Reconfiguration (DP-40), and other program areas, including Environmental Restoration and Waste Management (EM). To facilitate data collection, a questionnaire was developed and issued to nuclear materials custodian sites soliciting information on nuclear materials characteristics, storage plans, issues, etc. Sites were asked to functionally group materials identified in DOE Order 5660.1A (Management of Nuclear Materials) based on common physical and chemical characteristics and common material management strategies and to relate these groupings to Nuclear Materials Management Safeguards and Security (NMMSS) records. A database was constructed using 843 storage records from 70 responding sites. The database and an initial report summarizing storage issues were issued to participating Field Offices and DP-27 for comment. This report presents the background for the Storage Study and an initial, unclassified summary of storage issues and concerns identified by the sites

  6. Nuclear material operations manual

    International Nuclear Information System (INIS)

    Tyler, R.P.

    1981-02-01

    This manual provides a concise and comprehensive documentation of the operating procedures currently practiced at Sandia National Laboratories with regard to the management, control, and accountability of nuclear materials. The manual is divided into chapters which are devoted to the separate functions performed in nuclear material operations-management, control, accountability, and safeguards, and the final two chapters comprise a document which is also issued separately to provide a summary of the information and operating procedures relevant to custodians and users of radioactive and nuclear materials. The manual also contains samples of the forms utilized in carrying out nuclear material activities. To enhance the clarity of presentation, operating procedures are presented in the form of playscripts in which the responsible organizations and necessary actions are clearly delineated in a chronological fashion from the initiation of a transaction to its completion

  7. Nuclear material operations manuals

    International Nuclear Information System (INIS)

    Tyler, R.P.

    1979-06-01

    This manual is intended to provide a concise and comprehensive documentation of the operating procedures currently practiced at Sandia Laboratories with regard to the management, control, and accountability of radioactive and nuclear materials. The manual is divided into chapters which are devoted to the separate functions performed in nuclear material operations-management, control, accountability, and safeguards, and the final two chapters comprise a document which is also issued separately to provide a summary of the information and operating procedures relevant to custodians and users of radioactive and nuclear materials. The manual also contains samples of the forms utilized in carrying out nuclear material activities. To enhance the clarity of presentation, operating procedures are presented in the form of playscripts in which the responsible organizations and necessary actions are clearly delineated in a chronological fashion from the initiation of a transaction to its completion

  8. Selection of nuclear reactor coolant materials

    International Nuclear Information System (INIS)

    Shi Lisheng; Wang Bairong

    2012-01-01

    Nuclear material is nuclear material or materials used in nuclear industry, the general term, it is the material basis for the construction of nuclear power, but also a leader in nuclear energy development, the two interdependent and mutually reinforcing. At the same time, nuclear materials research, development and application of the depth and breadth of science and technology reflects a nation and the level of the nuclear power industry. Coolant also known as heat-carrier agent, is an important part of the heart nuclear reactor, its role is to secure as much as possible to the economic output in the form fission energy to heat the reactor to be used: the same time cooling the core, is controlled by the various structural components allowable temperature. This paper described the definition of nuclear reactor coolant and characteristics, and then addressed the requirements of the coolant material, and finally were introduced several useful properties of the coolant and chemical control. (authors)

  9. The law for the regulations of nuclear source materials, nuclear fuel materials and reactors

    International Nuclear Information System (INIS)

    1977-01-01

    Concerning refining, fabrication and reprocessing operations of such materials as well as the installation and operation of reactors, necessary regulations are carried out. Namely, in case of establishing the business of refining, fabricating and reprocessing nuclear materials as well as installing nuclear reactors, applications for the permission of the Prime Minister and the Minister of International Trade and Industry should be filed. Change of such operations should be permitted after filing applications. These permissions are retractable. As regards the reactors installed aboard foreign ships, it must be reported to enter Japanese waters and the permission by the Prime Minister must be obtained. In case of nuclear fuel fabricators, a chief technician of nuclear fuel materials (qualified) must be appointed per each fabricator. In case of installing nuclear reactors, the design and methods of construction should be permitted by the Prime Minister. The standard for such permission is specified, and a chief engineer for operating reactors (qualified) must be appointed. Successors inherit the positions of ones who have operated nuclear material refining, fabrication and reprocessing businesses or operated nuclear reactors. (Rikitake, Y.)

  10. Target values for nuclear material safeguards measurements - motivation or burden to operators?

    International Nuclear Information System (INIS)

    Weh, R.; Kuhn, K.D.

    1989-01-01

    The analytical determination of material streams and inventories plays an important part in those nuclear facilities called bulk-handling facilities in safeguards terminology. Reprocessing plants and mixed-oxide fabrication facilities are typical examples. With respect to their safeguards, the relevant regulations attach fundamental importance to material accountancy. The balance itself is examined by International Atomic Energy Agency (IAEA) inspectors and within the boundaries of the European Communities by Euratom inspectors as well, with regard to formal correctness. The analytical methods of accountancy in, for example, reprocessing plants, make high demands on the qualifications of the analyst. A conscientious analyst will, of course, try to fulfill his task as well and effectively as possible. These target values will become a burden, however, when they have been drawn up for purely scientific interest and the operator has been urged to achieve them on the pretext of improving safeguards. There are basically two reasons for which the authors have misgivings in this respect. First, the measurement system, which the material balance is based on, has to conform to the latest international regulations. This could easily lead to a permanent obligation of updating for the plants concerned. Second, the goal quantities set by the IAEA will induce an attempt to adjust measurement techniques and chemical analysis to goals totally unsuitable for large-scale plants

  11. Determination of technical details concerning measures for transportation of nuclear fuel materials in the works or the enterprise

    International Nuclear Information System (INIS)

    1979-01-01

    The determination is defined under the regulation for installation and operation of reactors for power generation. The limit of radioactive concentration of things contaminated by nuclear fuel materials which need not be sealed in a vessel is designated by the Minister of International Trade and Industry as 1/10,000 of A2 value per gram provided by another notification on transport of nuclear fuel materials outside the works. Measures for prevention of hazards shall be taken to stop flying out or leaking of radioactive substances by solidifying them with concrete or other hardening materials, not to let rain water penetrate into or to make each exterior side of transferred cubic things more than 10 centi-meters. The application for permission of things highly difficult to be enclosed in a vessel shall list name and address of the applicant, kind, quantity, form and nature of conveyed things contaminated by nuclear fuel materials, data and route of transfer and measures for prevention of hazards in transport. Radioactive doses specified by the minister are for an hour 200 mili-rem on the surface and 10 mili-rem at the distance of 1 meter from the surface of load, vehicle and container. Radioactive doses for the special loads shall be for an hour 1,000 mili-rem on the surface and 10 mili-rem at the distance of 2 meters from the surface of transferred things. (Okada, K.)

  12. Nuclear material operations manual

    International Nuclear Information System (INIS)

    Tyler, R.P.; Gassman, L.D.

    1978-04-01

    This manual is intended to provide a concise and comprehensive documentation of the operating procedures currently practiced at Sandia Laboratories with regard to the management, control, and accountability of radioactive and nuclear materials. The manual is divided into chapters which are devoted to the separate functions performed in nuclear material operations--management, control, accountability, and safeguards, and the final two chapters comprise a document which is also issued separately to provide a summary of the information and operating procedures relevant to custodians and users of radioactive and nuclear materials. The manual also contains samples of the forms utilized in carrying out nuclear material activities. To enhance the clarity of presentation, operating procedures are presented in the form of ''play-scripts'' in which the responsible organizations and necessary actions are clearly delineated in a chronological fashion from the initiation of a transaction to its completion

  13. Regulations concerning the fabricating business of nuclear fuel materials

    International Nuclear Information System (INIS)

    1985-01-01

    In the Law for the Regulations of Nuclear Source Material, Nuclear Fuel Material and Reactors, the regulations have all been revised on the fabrication business of nuclear fuel materials. The revised regulations are given : application for permission of the fabrication business, application for permission of the alteration, application for approval of the design and the construction methods, application for approval of the alteration, application for the facilities inspection, facilities inspection, recordings, entry limitations etc. for controlled areas, measures concerning exposure radiation doses etc., operation of the fabrication facilities, transport within the site of the business, storage, disposal within the site of the business, security regulations, designation etc. of the licensed engineer of nuclear fuels, collection of reports, etc. (Mori, K.)

  14. Nuclear materials management procedures

    International Nuclear Information System (INIS)

    Veevers, K.; Silver, J.M.; Quealy, K.J.; Steege, E. van der.

    1987-10-01

    This manual describes the procedures for the management of nuclear materials and associated materials at the Lucas Heights Research Laboratories. The procedures are designed to comply with Australia's nuclear non-proliferation obligations to the International Atomic Energy Agency (IAEA), bilateral agreements with other countries and ANSTO's responsibilities under the Nuclear Non-Proliferation (Safeguards) Act, 1987. The manual replaces those issued by the Australian Atomic Energy Commission in 1959, 1960 and 1969

  15. Material input of nuclear fuel

    International Nuclear Information System (INIS)

    Rissanen, S.; Tarjanne, R.

    2001-01-01

    The Material Input (MI) of nuclear fuel, expressed in terms of the total amount of natural material needed for manufacturing a product, is examined. The suitability of the MI method for assessing the environmental impacts of fuels is also discussed. Material input is expressed as a Material Input Coefficient (MIC), equalling to the total mass of natural material divided by the mass of the completed product. The material input coefficient is, however, only an intermediate result, which should not be used as such for the comparison of different fuels, because the energy contents of nuclear fuel is about 100 000-fold compared to the energy contents of fossil fuels. As a final result, the material input is expressed in proportion to the amount of generated electricity, which is called MIPS (Material Input Per Service unit). Material input is a simplified and commensurable indicator for the use of natural material, but because it does not take into account the harmfulness of materials or the way how the residual material is processed, it does not alone express the amount of environmental impacts. The examination of the mere amount does not differentiate between for example coal, natural gas or waste rock containing usually just sand. Natural gas is, however, substantially more harmful for the ecosystem than sand. Therefore, other methods should also be used to consider the environmental load of a product. The material input coefficient of nuclear fuel is calculated using data from different types of mines. The calculations are made among other things by using the data of an open pit mine (Key Lake, Canada), an underground mine (McArthur River, Canada) and a by-product mine (Olympic Dam, Australia). Furthermore, the coefficient is calculated for nuclear fuel corresponding to the nuclear fuel supply of Teollisuuden Voima (TVO) company in 2001. Because there is some uncertainty in the initial data, the inaccuracy of the final results can be even 20-50 per cent. The value

  16. Statistical methods for nuclear material management

    International Nuclear Information System (INIS)

    Bowen, W.M.; Bennett, C.A.

    1988-12-01

    This book is intended as a reference manual of statistical methodology for nuclear material management practitioners. It describes statistical methods currently or potentially important in nuclear material management, explains the choice of methods for specific applications, and provides examples of practical applications to nuclear material management problems. Together with the accompanying training manual, which contains fully worked out problems keyed to each chapter, this book can also be used as a textbook for courses in statistical methods for nuclear material management. It should provide increased understanding and guidance to help improve the application of statistical methods to nuclear material management problems

  17. Statistical methods for nuclear material management

    Energy Technology Data Exchange (ETDEWEB)

    Bowen W.M.; Bennett, C.A. (eds.)

    1988-12-01

    This book is intended as a reference manual of statistical methodology for nuclear material management practitioners. It describes statistical methods currently or potentially important in nuclear material management, explains the choice of methods for specific applications, and provides examples of practical applications to nuclear material management problems. Together with the accompanying training manual, which contains fully worked out problems keyed to each chapter, this book can also be used as a textbook for courses in statistical methods for nuclear material management. It should provide increased understanding and guidance to help improve the application of statistical methods to nuclear material management problems.

  18. Role of measurements in material control and accountability (abstract)

    International Nuclear Information System (INIS)

    Mahmud, T.

    2011-01-01

    Analytical techniques are widely used for verification and accountancy of nuclear materials. Nuclear Material (NM) inventories are based on sampling followed by Destructive Analysis. Destructive Analyses range from traditional chemical techniques to recent implementations of radiometric methods. These techniques are performed to quantify the amount of nuclear material (elemental assay and isotopic composition) present in a specific item, container, or in some cases facility and resolving shipper-receiver differences. Analytical techniques used for the MC and A of nuclear material normally require more attention than that for process control because the largest contribution to Material Unaccounted For is in measurement uncertainty. Therefore analytical techniques selected for material control and accountability are highly precise and they comply with accepted 'International Target Values 2010'. (author)

  19. Solution standards for quality control of nuclear-material analytical measurements

    International Nuclear Information System (INIS)

    Clark, J.P.

    1981-01-01

    Analytical chemistry measurement control depends upon reliable solution standards. At the Savannah River Plant Control Laboratory over a thousand analytical measurements are made daily for process control, product specification, accountability, and nuclear safety. Large quantities of solution standards are required for a measurement quality control program covering the many different analytical chemistry methods. Savannah River Plant produced uranium, plutonium, neptunium, and americium metals or oxides are dissolved to prepare stock solutions for working or Quality Control Standards (QCS). Because extensive analytical effort is required to characterize or confirm these solutions, they are prepared in large quantities. These stock solutions are diluted and blended with different chemicals and/or each other to synthesize QCS that match the matrices of different process streams. The target uncertainty of a standard's reference value is 10% of the limit of error of the methods used for routine measurements. Standard Reference Materials from NBS are used according to special procedures to calibrate the methods used in measuring the uranium and plutonium standards so traceability can be established. Special precautions are required to minimize the effects of temperature, radiolysis, and evaporation. Standard reference values are periodically corrected to eliminate systematic errors caused by evaporation or decay products. Measurement control is achieved by requiring analysts to analyze a blind QCS each shift a measurement system is used on plant samples. Computer evaluation determines whether or not a measurement is within the +- 3 sigma control limits. Monthly evaluations of the QCS measurements are made to determine current bias correction factors for accountability measurements and detect significant changes in the bias and precision statistics. The evaluations are also used to plan activities for improving the reliability of the analytical chemistry measurements

  20. Determination of internationally controlled materials according to provisions of the law for the regulations of nuclear source materials, nuclear fuel materials and reactors

    International Nuclear Information System (INIS)

    1981-01-01

    This rule is established under the provisions of the law concerning the regulation of nuclear raw materials, nuclear fuel materials and reactors, and the former notification No. 26, 1961, is hereby abolished. Internationally regulated goods under the law are as follows: nuclear raw materials, nuclear fuel materials and moderator materials transferred by sale or other means from the governments of the U.S., U.K., Canada, Australia and France or the persons under their jurisdictions according to the agreements concluded between the governments of Japan and these countries, respectively, the nuclear fuel materials recovered from these materials or produced by their usage, nuclear reactors, the facilities and heavy water transferred by sale or other means from these governments or the persons under their jurisdictions, the nuclear fuel materials produced by the usage of such reactors, facilities and heavy water, the nuclear fuel materials sold by the International Atomic Energy Agency under the contract between the Japanese government and the IAEA, the nuclear fuel materials recovered from these materials or produced by their usage, the heavy water produced by the facilities themselves transferred from the Canadian government, Canadian governmental enterprises or the persons under the jurisdiction of the Canadian government or produced by the usage of these facilities, etc. (Okada, K.)

  1. Bulk material management mode of general contractors in nuclear power project

    International Nuclear Information System (INIS)

    Zhang Jinyong; Zhao Xiaobo

    2011-01-01

    The paper introduces the characteristics of bulk material management mode in construction project, and the advantages and disadvantages of bulk material management mode of general contractors in nuclear power project. In combination with the bulk material management mode of China Nuclear Power Engineering Co., Ltd, some improvement measures have been put forward as well. (authors)

  2. Performance analysis of nuclear materials accounting systems

    International Nuclear Information System (INIS)

    Cobb, D.D.; Shipley, J.P.

    1979-01-01

    Techniques for analyzing the level of performance of nuclear materials accounting systems in terms of the four performance measures, total amount of loss, loss-detection time, loss-detection probability, and false-alarm probability, are presented. These techniques are especially useful for analyzing the expected performance of near-real-time (dynamic) accounting systems. A conservative estimate of system performance is provided by the CUSUM (cumulative summation of materials balances) test. Graphical displays, called performance surfaces, are developed as convenient tools for representing systems performance, and examples from a recent safeguards study of a nuclear fuels reprocessing plant are given. 6 refs

  3. Advanced research workshop: nuclear materials safety

    International Nuclear Information System (INIS)

    Jardine, L J; Moshkov, M M.

    1999-01-01

    The Advanced Research Workshop (ARW) on Nuclear Materials Safety held June 8-10, 1998, in St. Petersburg, Russia, was attended by 27 Russian experts from 14 different Russian organizations, seven European experts from six different organizations, and 14 U.S. experts from seven different organizations. The ARW was conducted at the State Education Center (SEC), a former Minatom nuclear training center in St. Petersburg. Thirty-three technical presentations were made using simultaneous translations. These presentations are reprinted in this volume as a formal ARW Proceedings in the NATO Science Series. The representative technical papers contained here cover nuclear material safety topics on the storage and disposition of excess plutonium and high enriched uranium (HEU) fissile materials, including vitrification, mixed oxide (MOX) fuel fabrication, plutonium ceramics, reprocessing, geologic disposal, transportation, and Russian regulatory processes. This ARW completed discussions by experts of the nuclear materials safety topics that were not covered in the previous, companion ARW on Nuclear Materials Safety held in Amarillo, Texas, in March 1997. These two workshops, when viewed together as a set, have addressed most nuclear material aspects of the storage and disposition operations required for excess HEU and plutonium. As a result, specific experts in nuclear materials safety have been identified, know each other from their participation in t he two ARW interactions, and have developed a partial consensus and dialogue on the most urgent nuclear materials safety topics to be addressed in a formal bilateral program on t he subject. A strong basis now exists for maintaining and developing a continuing dialogue between Russian, European, and U.S. experts in nuclear materials safety that will improve the safety of future nuclear materials operations in all the countries involved because of t he positive synergistic effects of focusing these diverse backgrounds of

  4. Development of data base system for nuclear material accountancy data at PNC

    International Nuclear Information System (INIS)

    Hirosawa, N.; Akiba, Mitsunori; Nakagima, Kiyoshi; Usui, Shinichi; Tosa, Kiyofumi; Hashimoto, Kazuyuki.

    1993-01-01

    PNC is developing a wide area of nuclear fuel cycle. Therefore, much nuclear material with a various form exists at each facility in the Works, and the controls of the inventory changes and the physical inventories of nuclear material are important. Nuclear material accountancy is a basic measure in safeguards system based on Non-Proliferation Treaty(NPT). In the light of such importance of material accountancy, the data base of nuclear material control and the material accountancy report system for all facilities has been developed by using the computer. By this system, accountancy report to STA is being presented certainly and timely. Property management and rapid corresponding to inquiries from STA can be carried out by the data base system which has free item searching procedure. The present paper introduces 'Development of Data Base System for Nuclear Material Accountancy Data at PNC'. (author)

  5. A new Brazilian regulation for the security of nuclear material and nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Tavares, Renato L.A.; Filho, Josélio S.M.; Torres, Luiz F.B.; Lima, Alexandre R., E-mail: renato.tavares@cnen.gov.br, E-mail: joselio@cnen.gov.br, E-mail: ltorres@cnen.gov.br, E-mail: alexandre.lima@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Diretoria de Radioproteção e Segurança Nuclear; Lima, Fabiano P.C., E-mail: fabianopetruceli@outlook.com [Presidência da República, Brasilia, DF (Brazil). Gabinete de Segurança Institucional

    2017-07-01

    The present paper aims to outline the challenges related to the elaboration and concepts involved in a regulatory transition from a purely prescriptive approach to a combined approach that mixes performance-based concepts and evaluation metrics based on statistical data of equipment and personnel. This methodology might represent an improvement compared to a purely prescriptive approach, in which the regulatory authority defines the measures to be taken by operators of nuclear facilities to prevent theft, sabotage events, and mitigate their consequences. The prescriptive approach, despite having the advantages of clarity in the definition of requirements, simplicity in regulatory terms (inspections to verify compliance), and homogeneity in relation to various facilities, does not allow a clear and effective performance measurement, may provide insufficient or excessive security measures (with excessive expenditure of material and human resources), and the possibility of providing a false sense of security. It is known that, in many countries, the state-sponsored nuclear security regime mixes elements of the two mentioned approaches, prescriptive and based on performance, which is not Brazilian practice nowadays. Such methodological developments happened globally due to the increase of threat level for nuclear facilities and materials. The currently regulation in force is CNEN-NE 2.01, which provides a set of measures intended to implement Physical Protection Systems in Nuclear, Radiological Facilities as well as Transport Operations, and all documents related to security of such issues. The new regulation, named CNEN-NN 2.01, will focus only on Nuclear Material and Facilities (two other regulations specific for Security of Radioactive Sources and Transport Operations are under elaboration process). CNEN NN 2.01 is intended to provide further adherence to new international recommendations, e.g, IAEA INFCIRC 225 Rev.5 (NSS 13), which is currently regarded as the

  6. A new Brazilian regulation for the security of nuclear material and nuclear facilities

    International Nuclear Information System (INIS)

    Tavares, Renato L.A.; Filho, Josélio S.M.; Torres, Luiz F.B.; Lima, Alexandre R.; Lima, Fabiano P.C.

    2017-01-01

    The present paper aims to outline the challenges related to the elaboration and concepts involved in a regulatory transition from a purely prescriptive approach to a combined approach that mixes performance-based concepts and evaluation metrics based on statistical data of equipment and personnel. This methodology might represent an improvement compared to a purely prescriptive approach, in which the regulatory authority defines the measures to be taken by operators of nuclear facilities to prevent theft, sabotage events, and mitigate their consequences. The prescriptive approach, despite having the advantages of clarity in the definition of requirements, simplicity in regulatory terms (inspections to verify compliance), and homogeneity in relation to various facilities, does not allow a clear and effective performance measurement, may provide insufficient or excessive security measures (with excessive expenditure of material and human resources), and the possibility of providing a false sense of security. It is known that, in many countries, the state-sponsored nuclear security regime mixes elements of the two mentioned approaches, prescriptive and based on performance, which is not Brazilian practice nowadays. Such methodological developments happened globally due to the increase of threat level for nuclear facilities and materials. The currently regulation in force is CNEN-NE 2.01, which provides a set of measures intended to implement Physical Protection Systems in Nuclear, Radiological Facilities as well as Transport Operations, and all documents related to security of such issues. The new regulation, named CNEN-NN 2.01, will focus only on Nuclear Material and Facilities (two other regulations specific for Security of Radioactive Sources and Transport Operations are under elaboration process). CNEN NN 2.01 is intended to provide further adherence to new international recommendations, e.g, IAEA INFCIRC 225 Rev.5 (NSS 13), which is currently regarded as the

  7. Regulations concerning the transport of nuclear fuel materials outside the works or the enterprise

    International Nuclear Information System (INIS)

    1979-01-01

    The regulations are defined under the law for the regulations of nuclear source materials, nuclear fuel materials and reactors and the order for execution of the law. Basic concepts and terms are explained, such as: vehicle transport; easy transport; nuclear fuel material load, exclusive loading, employee, accumulative dose and exposure dose. Technical standards of vehicle transport are specified in detail on nucler fuel materials as nuclear fuel load, L,A, EM and BU type of load, nuclear fuel load of fission substances, the second and third type of fission load and materials contaminated by nuclear fuel substances to be carried not as nuclear fuel loads. Special exceptional measures to such transport and technical standards of easy transport are also designated. The application for confirmation of the transport shall be filed to the Director General of Science and Technology Agency according to the form attached with documents explaining nuclear fuel materials to be transferred, the vessel of such materials and construction, material and method of production of such a vessel, safety of nuclear materials contained, etc. Measures in dangerous situations shall be taken to fight a fire or prohibit the entrance of persons other than the staff concerned. Reports shall be presented in 10 days to the Director, when theft, loss or irregular leaking of nuclear fuel materials or personal troubles occur on the way. (Okada, K.)

  8. Nuclear Fuels & Materials Spotlight Volume 5

    International Nuclear Information System (INIS)

    Petti, David Andrew

    2016-01-01

    As the nation's nuclear energy laboratory, Idaho National Laboratory brings together talented people and specialized nuclear research capability to accomplish our mission. This edition of the Nuclear Fuels and Materials Division Spotlight provides an overview of some of our recent accomplishments in research and capability development. These accomplishments include: • Evaluation and modeling of light water reactor accident tolerant fuel concepts • Status and results of recent TRISO-coated particle fuel irradiations, post-irradiation examinations, high-temperature safety testing to demonstrate the accident performance of this fuel system, and advanced microscopy to improve the understanding of fission product transport in this fuel system. • Improvements in and applications of meso and engineering scale modeling of light water reactor fuel behavior under a range of operating conditions and postulated accidents (e.g., power ramping, loss of coolant accident, and reactivity initiated accidents) using the MARMOT and BISON codes. • Novel measurements of the properties of nuclear (actinide) materials under extreme conditions, (e.g. high pressure, low/high temperatures, high magnetic field) to improve the scientific understanding of these materials. • Modeling reactor pressure vessel behavior using the GRIZZLY code. • New methods using sound to sense temperature inside a reactor core. • Improved experimental capabilities to study the response of fusion reactor materials to a tritium plasma. Throughout Spotlight, you'll find examples of productive partnerships with academia, industry, and government agencies that deliver high-impact outcomes. The work conducted at Idaho National Laboratory helps spur innovation in nuclear energy applications that drive economic growth and energy security. We appreciate your interest in our work here at Idaho National Laboratory, and hope that you find this issue informative.

  9. 10 CFR 74.33 - Nuclear material control and accounting for uranium enrichment facilities authorized to produce...

    Science.gov (United States)

    2010-01-01

    ... and special nuclear material in the accounting records are based on measured values; (3) A measurement... 10 Energy 2 2010-01-01 2010-01-01 false Nuclear material control and accounting for uranium... Section 74.33 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL...

  10. Smuggling special nuclear materials

    International Nuclear Information System (INIS)

    Lazaroiu, Gheorghe

    1999-01-01

    Ever since the collapse of the former Soviet Union reports have circulated with increasing frequency concerning attempts to smuggle materials from that country's civil and military nuclear programs. Such an increase obviously raises a number of concerns (outlined in the author's introduction), chief among which is the possibility that these materials might eventually fall into the hands of proliferant states or terrorist groups. The following issues are presented: significance of materials being smuggled; sources and smuggling routes; potential customers; international efforts to reduce nuclear smuggling; long-term disposition of fissile materials. (author)

  11. Measurement techniques for the verification of excess weapons materials

    International Nuclear Information System (INIS)

    Tape, J.W.; Eccleston, G.W.; Yates, M.A.

    1998-01-01

    The end of the superpower arms race has resulted in an unprecedented reduction in stockpiles of deployed nuclear weapons. Numerous proposals have been put forward and actions have been taken to ensure the irreversibility of nuclear arms reductions, including unilateral initiatives such as those made by President Clinton in September 1993 to place fissile materials no longer needed for a deterrent under international inspection, and bilateral and multilateral measures currently being negotiated. For the technologist, there is a unique opportunity to develop the technical means to monitor nuclear materials that have been declared excess to nuclear weapons programs, to provide confidence that reductions are taking place and that the released materials are not being used again for nuclear explosive programs. However, because of the sensitive nature of these materials, a fundamental conflict exists between the desire to know that the bulk materials or weapon components in fact represent evidence of warhead reductions, and treaty commitments and national laws that require the protection of weapons design information. This conflict presents a unique challenge to technologists. The flow of excess weapons materials, from deployed warheads through storage, disassembly, component storage, conversion to bulk forms, and disposition, will be described in general terms. Measurement approaches based on the detection of passive or induced radiation will be discussed along with the requirement to protect sensitive information from release to unauthorized parties. Possible uses of measurement methods to assist in the verification of arms reductions will be described. The concept of measuring attributes of items rather than quantitative mass-based inventory verification will be discussed along with associated information-barrier concepts required to protect sensitive information

  12. Nuclear battery materials and application of nuclear batteries

    International Nuclear Information System (INIS)

    Hao Shaochang; Lu Zhenming; Fu Xiaoming; Liang Tongxiang

    2006-01-01

    Nuclear battery has lots of advantages such as small volume, longevity, environal stability and so on, therefore, it was widely used in aerospace, deep-sea, polar region, heart pacemaker, micro-electromotor and other fields etc. The application of nuclear battery and the development of its materials promote each other. In this paper the development and the latest research progress of nuclear battery materials has been introduced from the view of radioisotope, electric energy conversion and encapsulation. And the current and potential applications of the nuclear battery are also summarized. (authors)

  13. ORACL program file for acquisition, storage and analysis of data in radiation measurement and nondestructive measurement of nuclear material, vol. 2

    International Nuclear Information System (INIS)

    Yagi, Hideyuki; Takeuchi, Norio; Gotoh, Hiroshi

    1976-09-01

    The file contains 79 programs for radiation measurement and nondestructive measurement of nuclear material written in conversational language ORACL associated with the GAMMA-III system of ORTEC Incorporated. It deals with data transfers between disk/core/MCA/magnetic tape, edition of data in disks, calculation of the peak area, calculation of mean and standard deviation, reference to gamma-ray data files, accounting, calendar, etc. It also has a support system for micro-computer development. Usages of the built-in functions of ORACL are presented. (auth.)

  14. Requirements for near-real-time accounting of strategic nuclear materials in nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Hakkila, E.A.; Cobb, D.D.; Dietz, R.J.; Shipley, J.P.; Smith, D.B.

    1978-01-01

    A Purex-based nuclear fuel reprocessing plant has been studied for possible incorporation of near-real-time accounting to supplement conventional accounting procedures. Near-real-time accounting of special nuclear materials relies on in-line or at-line flow measurements and plutonium assay of product and waste streams, complemented by conventional analytical chemistry for daily instrument calibrations. In-line alpha monitors could be used for waste stream measurements of plutonium, even in the presence of high beta-gamma fluxes from fission products. X-ray absorption edge densitometry using either K- or L-absorption edges could be used for plutonium concentration measurements in main product streams. Some problem areas identified in waste stream measurements include measurements of leached hulls and of centrifuge sludge. Conventional analytical chemical methods for measuring plutonium in weapons grade material can be modified for reprocessed plutonium. Analytical techniques requiring special precautions will be reviewed

  15. Ordinance concerning the filing of transport of nuclear fuel materials

    International Nuclear Information System (INIS)

    1979-01-01

    The ordinance is defined under the law for the regulations of nuclear source materials, nuclear fuel materials and reactors and the order for execution of the law. Any person who reports the transport of nuclear fuel materials shall file four copies of a notification according to the form attached to the public safety commission of the prefecture in charge of the dispatching place. When the transportation extends over the area in charge of another public safety commission, the commission which has received the notice shall report without delay date and route of the transport, kind and quantity of nuclear fuel materials and other necessary matters to the commission concerned and hear from the latter opinions on the items informed. The designation by the ordinance includes speed of the vehicle loaded with nuclear fuel materials, disposition of an accompanying car, arrangement of the line of the loaded vehicle and accompanying and other escorting cars, location of the parking, place of unloading and temporary storage, etc. Reports concerning troubles and measures taken shall be filed in ten days to the public safety commission which has received the notification, when accidents occur on the way, such as: theft or loss of nuclear fuel materials; traffic accident; irregular leaking of nuclear fuel materials and personal trouble by the transport. (Okada, K.)

  16. Application of Nuclear Forensics in Combating Illicit Trafficking of Nuclear and Other Radioactive Material

    International Nuclear Information System (INIS)

    2014-01-01

    As a scientific discipline, nuclear forensics poses formidable scientific challenges with regard to extracting information on the history, origin, movement and processing of nuclear and other radioactive material found to be out of regulatory control. Research into optimized techniques is being pursued by leading nuclear forensic research groups around the world. This research encompasses areas including evidence collection, analytical measurements for rapid and reliable categorization and characterization of nuclear and radioactive material, and interpretation using diverse data characteristics or the 'science of signatures' from throughout the nuclear fuel cycle. In this regard, the IAEA recently concluded the Coordinated Research Project (CRP) entitled Application of Nuclear Forensics in Illicit Trafficking of Nuclear and Other Radioactive Material. The CRP seeks to improve the ability of Member States to provide robust categorization and characterization of seized material, reliable techniques for the collection and preservation of nuclear forensic evidence, and the ability to interpret the results for law enforcement and other purposes. In accordance with broader IAEA objectives, the CRP provides a technical forum for participating institutes from Member States to exchange technical information to benefit national confidence building as well as to advance the international discipline of nuclear forensics. This CRP was initially planned in 2006, commenced in 2008 and was completed in 2012. Three research coordination meetings (RCM) were convened at the IAEA in Vienna to review progress. The leadership of the chairpersons was essential to establishing the technical viability of nuclear forensics at the IAEA and with the Member States

  17. The Physical Protection of Nuclear Material; Proteccion Fisica Delos Materiales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-09-15

    Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international cooperation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and materials, particularly when such materials are transported across national frontiers [French] La proteccion fisica contra el robo o la desviacion no autorizada de materiales nucleares y contra el sabotaje de las instalaciones nucleares por parte de individuos o de grupos ha sido durante largo tiempo motivo de preocupacion nacional e internacional. Aunque la obligacion de crear y hacer funcionar un sistema completo de proteccion fisica para las instalaciones y materiales nucleares en el territorio de un Estado determinado incumbe enteramente al Gobierno de dicho Estado, el que esa obligacion se cumpla o no, y si se cumple, en que medida o hasta que punto, es cosa que no deja indiferentes a los demas Estados. De aqui que la proteccion fisica se haya convertido en motivo de interes y cooperacion internacional. La necesidad de cooperacion internacional se hace evidente en los casos en que la eficacia de la proteccion fisica en el territorio de un Estado depende de que otros Estados tomen tambien medidas apropiadas para evitar o hacer fracasar los actos hostiles dirigidos contra instalaciones y

  18. Fixed-wing gamma measurement for the detection of radioactive materials

    International Nuclear Information System (INIS)

    Kettunen, M.J.; Nikkinen, M.T.

    2005-01-01

    Finland has the operational capability to take airborne gamma-ray measurements in emergency situations. The original purpose of airborne radiation mapping in Finland was to identify hazardous areas containing radioactive fall-out after a nuclear accident or use of nuclear weapons. Regular exercises are held annually to keep the operational functionality at a high level. The achieved capability has been well demonstrated in international INEX-2-FIN 1997 and Barents Rescue 2001 exercises. The knowledge and competence achieved can easily be applied in international radiation monitoring campaigns designed to expose undeclared nuclear materials or other clandestine nuclear activities. The essential improvements in the detection system are linked to the ability to locate point-like radiation sources rather than large areas of fall-out. Aerial gamma-ray measurement method and its usability for the detection of nuclear material production chains and trails of fission or activation products is described. The ability of airborne detection systems in revealing the use of undeclared nuclear materials has been tested. Various scenarios for exposing clandestine nuclear material production, enrichment and nuclear waste trails have been considered. Based on detection capability calculations and testing in practice, it was found that the detection of one un-shielded significant quantity of natural uranium (10 tons of yellow cake in storage barrels) is possible through the daughter products, using one single 6' x 4' NaI detector on the airplane. The developed fixed wing gamma measurement technique is now able to detect significant amounts of nuclear material conveniently and cost-effectively. Large areas can be screened to identify suspicious sub-areas for more detailed ground-based inspection. (author)

  19. Determination of internationally controlled materials according to provisions of the law for the regulations of nuclear source materials, nuclear fuel materials and reactors

    International Nuclear Information System (INIS)

    1977-01-01

    According to the provisions of The Law, those stipulated as internationally controlled materials are nuclear source materials, nuclear fuel materials, moderating materials, reactors and facilities, transferred from such as the U.S.A., the U.K. and Canada on the agreements of peaceful uses of atomic energy, and nuclear fuel materials accruing therefrom. (Mori, K.)

  20. Thermodynamics of nuclear materials

    International Nuclear Information System (INIS)

    1962-01-01

    The first session of the symposium discussed in general the thermodynamic properties of actinides, including thorium, uranium and Plutonium which provide reactor fuel. The second session was devoted to applications of thermodynamic theory to the study of nuclear materials, while the experimental techniques for the determination of thermodynamic data were examined at the next session. The thermodynamic properties of alloys were considered at a separate session, and another session was concerned with solids other than alloys. Vaporization processes, which are of special interest in the development of high-temperature reactors, were discussed at a separate session. The discussions on the methods of developing the data and ascertaining their accuracy were especially useful in highlighting the importance of determining whether any given data are reliable before they can be put to practical application. Many alloys and refractory materials (i. e. materials which evaporate only at very high temperatures) are of great importance in nuclear technology, and some of these substances are extremely complex in their chemical composition. For example, until recently the phase composition of the oxides of thorium, uranium and plutonium had been only very imperfectly understood, and the same was true of the carbides of these elements. Recent developments in experimental techniques have made it possible to investigate the phase composition of these complex materials as well as the chemical species of these materials in the gaseous phase. Recent developments in measuring techniques, such as fluorine bomb calorimetry and Knudsen effusion technique, have greatly increased the accuracy of thermodynamic data

  1. Chapter No.5. Nuclear materials and physical protection of nuclear installations

    International Nuclear Information System (INIS)

    2002-01-01

    The State System of Accounting for and Control of Nuclear Material (SSAC) is based on requirements resulting from the Safeguards Agreement between the Government of the Slovak Republic and the IAEA. UJD performs this activity according to the 'Atomic Act' and relevant decree. The purpose of the SSAC is also to prevent unauthorised use of nuclear materials, to detect loses of nuclear materials and provide information that could lead to the recovery of missing material. The main part of nuclear materials under jurisdiction of the Slovak Republic is located at NPP Jaslovske Bohunice, NPP Mochovce and at interim storage in Jaslovske Bohunice. Even though that there are located more then 99% of nuclear materials in these nuclear facilities, there are not any significant problems with their accountancy and control due to very simply identification of accountancy units - fuel assemblies, and due to stability of legal subjects responsible for operation and for keeping of information continuity, which is necessary for fulfilling requirements of the Agreement. The nuclear material located outside nuclear facilities is a special category. There are 81 such subjects of different types and orientations on the territory of the Slovak Republic. These subjects use mainly depleted uranium as a shielding and small quantity of natural uranium, low enrichment uranium and thorium for experimental purposes and education. Frequent changes of these subjects, their transformations into the other subjects, extinction and very high fluctuation of employees causes loss of information about nuclear materials and creates problems with fulfilling requirements resulting from the Agreement. In 2001, the UJD carried out 51 inspections of nuclear materials, of which 31 inspections were performed at nuclear installations in co-operation with the IAEA inspectors. No discrepancies concerning the management of nuclear materials were found out during inspections and safeguards goals in year 2001 were

  2. Central Bureau for Nuclear Measurements

    International Nuclear Information System (INIS)

    1991-01-01

    The main task of CBNM is defined as the specific programme Nuclear Measurements and Reference Materials. In the field of neutron data for standards, for fission and for fusion application, the nuclear charge distribution and odd-even effects for mass, charge and neutron number in the cold spontaneous fission of 252 Cf were determined. X- and γ-ray emission probabilities were evaluated in the frame of an IAEA coordinated Research Project. The subthermal fission cross section measurements of 235 U, 233 U and 239 Pu, were finalised. The dependence of the experimental weighting function of C 6 D 6 detectors on thickness of several 56 Fe samples was determined. Fusion data studies involved the development of a light-ion telescope with improved time - and energy resolution. Double differential cross-sections of 9 Be were analysed. Radionuclide metrology dealt with the response of silicon detectors, as well as with the standardization of 192 Ir sources. Project Reference Materials reports the EC Certification of nuclear reference materials 210 (PuO 2 ), 523 (Al), 525 (Nb) and 526 (Nb). Progress was achieved in the preparation of dried solid spikes of uranium and plutonium for undiluted reprocessing input solution analysis. 10 B and 6 Li deposits were prepared for a redetermination of the neutron lifetime. Preliminary studies on speciation of trace metals in biological fluids were successful. Radioactive waste barrels were analysed by γ-scanning and blood samples were irradiated with 0.6 MeV neutrons. Exploratory research resulted in first measurements of transition radiation properties

  3. Thermodynamics of nuclear materials

    International Nuclear Information System (INIS)

    Rand, M.H.

    1975-01-01

    A report is presented of the Fourth International Symposium on Thermodynamics of Nuclear Materials held in Vienna, 21-25 October 1974. The technological theme of the Symposium was the application of thermodynamics to the understanding of the chemistry of irradiated nuclear fuels and to safety assessments for hypothetical accident conditions in reactors. The first four sessions were devoted to these topics and they were followed by four more sessions on the more basic thermodynamics, phase diagrams and the thermodynamic properties of a wide range of nuclear materials. Sixty-seven papers were presented

  4. Material accountancy measurement techniques in dry-powdered processing of nuclear spent fuels

    International Nuclear Information System (INIS)

    Wolf, S. F.

    1999-01-01

    The paper addresses the development of inductively coupled plasma-mass spectrometry (ICPMS), thermal ionization-mass spectrometry (TIMS), alpha-spectrometry, and gamma spectrometry techniques for in-line analysis of highly irradiated (18 to 64 GWD/T) PWR spent fuels in a dry-powdered processing cycle. The dry-powdered technique for direct elemental and isotopic accountancy assay measurements was implemented without the need for separation of the plutonium, uranium and fission product elements in the bulk powdered process. The analyses allow the determination of fuel burn-up based on the isotopic composition of neodymium and/or cesium. An objective of the program is to develop the ICPMS method for direct fissile nuclear materials accountancy in the dry-powdered processing of spent fuel. The ICPMS measurement system may be applied to the KAERI DUPIC (direct use of spent PWR fuel in CANDU reactors) experiment, and in a near-real-time mode for international safeguards verification and non-proliferation policy concerns

  5. Global nuclear material flow/control model

    International Nuclear Information System (INIS)

    Dreicer, J.S.; Rutherford, D.S.; Fasel, P.K.; Riese, J.M.

    1997-01-01

    This is the final report of a two-year, Laboratory Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). The nuclear danger can be reduced by a system for global management, protection, control, and accounting as part of an international regime for nuclear materials. The development of an international fissile material management and control regime requires conceptual research supported by an analytical and modeling tool which treats the nuclear fuel cycle as a complete system. The prototype model developed visually represents the fundamental data, information, and capabilities related to the nuclear fuel cycle in a framework supportive of national or an international perspective. This includes an assessment of the global distribution of military and civilian fissile material inventories, a representation of the proliferation pertinent physical processes, facility specific geographic identification, and the capability to estimate resource requirements for the management and control of nuclear material. The model establishes the foundation for evaluating the global production, disposition, and safeguards and security requirements for fissile nuclear material and supports the development of other pertinent algorithmic capabilities necessary to undertake further global nuclear material related studies

  6. Techniques and methods in nuclear materials traceability

    International Nuclear Information System (INIS)

    Persiani, P.J.

    1996-01-01

    The nonproliferation community is currently addressing concerns that the access to special nuclear materials may increase the illicit trafficking in weapons-usable materials from civil and/or weapons material stores and/or fuel cycles systems. Illicit nuclear traffic usually involves reduced quantities of nuclear materials perhaps as samplings of a potential protracted diversionary flow from sources to users. To counter illicit nuclear transactions requires the development of techniques and methods in nuclear material traceability as an important phase of a broad forensic analysis capability. This report discusses how isotopic signatures and correlation methods were applied to determine the origins of Highly Enriched Uranium (HEU) and Plutonium samples reported as illicit trafficking in nuclear materials

  7. Nuclear Fuels & Materials Spotlight Volume 5

    Energy Technology Data Exchange (ETDEWEB)

    Petti, David Andrew [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-10-01

    As the nation's nuclear energy laboratory, Idaho National Laboratory brings together talented people and specialized nuclear research capability to accomplish our mission. This edition of the Nuclear Fuels and Materials Division Spotlight provides an overview of some of our recent accomplishments in research and capability development. These accomplishments include: • Evaluation and modeling of light water reactor accident tolerant fuel concepts • Status and results of recent TRISO-coated particle fuel irradiations, post-irradiation examinations, high-temperature safety testing to demonstrate the accident performance of this fuel system, and advanced microscopy to improve the understanding of fission product transport in this fuel system. • Improvements in and applications of meso and engineering scale modeling of light water reactor fuel behavior under a range of operating conditions and postulated accidents (e.g., power ramping, loss of coolant accident, and reactivity initiated accidents) using the MARMOT and BISON codes. • Novel measurements of the properties of nuclear (actinide) materials under extreme conditions, (e.g. high pressure, low/high temperatures, high magnetic field) to improve the scientific understanding of these materials. • Modeling reactor pressure vessel behavior using the GRIZZLY code. • New methods using sound to sense temperature inside a reactor core. • Improved experimental capabilities to study the response of fusion reactor materials to a tritium plasma. Throughout Spotlight, you'll find examples of productive partnerships with academia, industry, and government agencies that deliver high-impact outcomes. The work conducted at Idaho National Laboratory helps spur innovation in nuclear energy applications that drive economic growth and energy security. We appreciate your interest in our work here at Idaho National Laboratory, and hope that you find this issue informative.

  8. Meeting of socialist conntries' representatives on problems of nuclear materials analyses

    International Nuclear Information System (INIS)

    Pacak, P.; Moravec, J.; Krtil, J.; Sus, F.

    1982-01-01

    A meeting of representatives of the socialist countries was held in Prague from May 18 to 22, 1981, to discuss cooperation in the field of analytical control of nuclear materials. The Czechoslovak delegation informed the participants of the extent and results of the work of the Central Control Laboratory of the Nuclear Research Institute in Rez. A brief survey is given of the nondestructive methods of measuring the physical parameters of nuclear fuel, the methods of destructive determination of uranium and plutonium and the methods of preparation of standard materials for mass spectrometry which the Central Control Laboratory has introduced and verified for securing analytical control of nuclear materials. (B.S.)

  9. Control of nuclear material specified equipment and specified material

    International Nuclear Information System (INIS)

    1982-04-01

    The goal and application field of NE 2.02 regulatory guide of CNEN (Comissao Nacional de Energia Nuclear), are described. This regulatory guide is about nuclear material management, specified equipment and specified material. (E.G.) [pt

  10. Physical protection of nuclear material

    International Nuclear Information System (INIS)

    1975-01-01

    Full text: An Advisory Group met to consider the up-dating and extension of the Recommendations for the Physical Protection of Nuclear Material, produced in 1972. Twenty-seven experts from 11 countries and EURATOM were present. Growing concern has been expressed in many countries that nuclear material may one day be used for acts of sabotage or terrorism. Serious attention is therefore being given to the need for States to develop national systems for the physical protection of nuclear materials during use, storage and transport throughout the nuclear fuel cycle which should minimize risks of sabotage or theft. The revised Recommendations formulated by the Advisory Group include new definitions of the objectives of national systems of physical protection and proposals for minimizing possibilities of unauthorized removal and sabotage to nuclear facilities. The Recommendations also describe administrative or organizational steps to be taken for this purpose and the essential technical requirements of physical protection for various types and locations of nuclear material, e.g., the setting up of protected areas, the use of physical barriers and alarms, the need for security survey, and the need of advance arrangements between the States concerned in case of international transportation, among others. (author)

  11. Evaluation of excess nuclear materials suitability for international safeguards

    International Nuclear Information System (INIS)

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

    1996-01-01

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

  12. Nuclear science in the 20th century. Nuclear technology applications in material science

    International Nuclear Information System (INIS)

    Pei Junchen; Xu Furong; Zheng Chunkai

    2003-01-01

    The application of nuclear technology to material science has led to a new cross subject, nuclear material science (also named nuclear solid physics) which covers material analysis, material modification and new material synthesis. This paper reviews the development of nuclear technical applications in material science and the basic physics involved

  13. Expanding Nuclear Power Programmes - Romanian experience: Master - Nuclear Materials and Technologies Educational Plan

    International Nuclear Information System (INIS)

    Valeca, S.; Valeca, M.

    2012-01-01

    The main objectives of the Master Nuclear Materials and Technologies Educational Plan are: 1. To deliver higher education and training in the following specific domains, such as: Powders Technology and Ceramic Materials, Techniques of Structural Analysis, Composite Materials, Semiconductor Materials and Components, Metals and Metallic Alloys, Optoelectronic Materials and Devices, Nuclear Materials, The Engineering of Special Nuclear Materials, 2. To train managers of the Nuclear Waste Products and Nuclear Safety, 3. To qualify in ICT Systems for Nuclear Process Guidance, 4. To qualify in Environmental Protection System at the Level of Nuclear Power Stations, 5. To train managers for Quality Assurance of Nuclear Energetic Processes, 6. To deliver higher education and training regarding the International Treatises, Conventions and Settlements in force in the field of nuclear related activities. (author)

  14. United States Department of Energy Nuclear Materials Stewardship

    International Nuclear Information System (INIS)

    Newton, J. W.

    2002-01-01

    The Department of Energy launched the Nuclear Materials Stewardship Initiative in January 2000 to accelerate the work of achieving integration and cutting long-term costs associated with the management of the Department's nuclear materials, with the principal focus on excess materials. Management of nuclear materials is a fundamental and enduring responsibility that is essential to meeting the Department's national security, nonproliferation, energy, science, and environmental missions into the distant future. The effective management of nuclear materials is important for a set of reasons: (1) some materials are vital to our national defense; (2) the materials pose physical and security risks; (3) managing them is costly; and (4) costs are likely to extend well into the future. The Department currently manages nuclear materials under eight programs, with offices in 36 different locations. Through the Nuclear Materials Stewardship Initiative, progress was during calendar year 20 00 in achieving better coordination and integration of nuclear materials management responsibilities and in evaluating opportunities to further coordinate and integrate cross-program responsibilities for the treatment, storage, and disposition of excess nuclear materials. During CY 2001 the Departmental approach to nuclear materials stewardship changed consistent with the business processes followed by the new administration. This paper reports on the progress of the Nuclear Materials Stewardship Initiative in evaluating and implementing these opportunities, and the remaining challenges in integrating the long-term management of nuclear materials

  15. Preliminary assessment on the differences of nuclear terrorism convention from the convention on the physical protection of nuclear material and amendment to the convention on the physical protection of nuclear material

    International Nuclear Information System (INIS)

    Midiana Ariethia; Muhamad Ilman A A; Mas Pungky Hendrawijaya

    2011-01-01

    The threat of acts of nuclear terrorism in all its forms and manifestations create the urgent need to enhance international cooperation between countries in designing and following practical and effective measures for the prevention of acts of terrorism and to counter and punish its offenders. Several United Nations Security Council Resolutions, such as UNSCR Number 1373 (2001), and UNSCR Number 1540 (2005), and the result of Nuclear Security Summit in 2010 that encourage the member countries of IAEA to ratify nuclear conventions as soon as possible, are the reasons that the Indonesian Government planning on ratifying The International Convention for The Suppression of Acts of Nuclear Terrorism (Nuclear Terrorism Convention). Nuclear Terrorism Convention is one of the 16 (sixteen) international instruments that must be ratified by the member countries of IAEA. Of the 16 (sixteen) international instruments, 3 (three) conventions are related to nuclear; Convention on the Physical Protection of Nuclear Material, Amendment to the Convention on the Physical Protection of Nuclear Material, dan Nuclear Terrorism Convention. This paper presents the preliminary assessment on the differences of Nuclear Terrorism Convention to The Convention on The Physical Protection of Nuclear Material and Amendment to The Convention on The Physical Protection of Nuclear Material. This assessment is important due to the plan of the Indonesian Government to ratify the Nuclear Terrorism Convention. The result of this assessment could be used by BAPETEN in the ratification process of the Nuclear Terrorism Convention. The method used in this assessment is references assessment. (author)

  16. [Measures against Radiation Exposure Due to Large-Scale Nuclear Accident in Distant Place--Radioactive Materials in Nagasaki from Fukushima Daiichi Nuclear Power Plant].

    Science.gov (United States)

    Yuan, Jun; Sera, Koichiro; Takatsuji, Toshihiro

    2015-01-01

    To investigate human health effects of radiation exposure due to possible future nuclear accidents in distant places and other various findings of analysis of the radioactive materials contaminating the atmosphere of Nagasaki due to the Fukushima Daiichi Nuclear Power Plant accident. The concentrations of radioactive materials in aerosols in the atmosphere of Nagasaki were measured using a germanium semiconductor detector from March 2011 to March 2013. Internal exposure dose was calculated in accordance with ICRP Publ. 72. Air trajectories were analyzed using NOAA and METEX web-based systems. (134)Cs and (137)Cs were repeatedly detected. The air trajectory analysis showed that (134)Cs and (137)Cs flew directly from the Fukushima Daiichi Nuclear Power Plant from March to April 2011. However, the direct air trajectories were rarely detected after this period even when (134)Cs and (137)Cs were detected after this period. The activity ratios ((134)Cs/(137)Cs) of almost all the samples converted to those in March 2011 were about unity. This strongly suggests that the (134)Cs and (137)Cs detected mainly originated from the Fukushima Daiichi Nuclear Power Plant accident in March 2011. Although the (134)Cs and (137)Cs concentrations per air volume were very low and the human health effects of internal exposure via inhalation is expected to be negligible, the specific activities (concentrations per aerosol mass) were relatively high. It was found that possible future nuclear accidents may cause severe radioactive contaminations, which may require radiation exposure control of farm goods to more than 1000 km from places of nuclear accidents.

  17. The law for the regulations of nuclear source materials, nuclear fuel materials and reactors

    International Nuclear Information System (INIS)

    1980-01-01

    The law intends under the principles of the atomic energy act to regulate the refining, processing and reprocessing businesses of nuclear raw and fuel metarials and the installation and operation of reactors for the peaceful and systematic utilization of such materials and reactors and for securing public safety by preventing disasters, as well as to control internationally regulated things for effecting the international agreements on the research, development and utilization of atomic energy. Basic terms are defined, such as atomic energy; nuclear fuel material; nuclear raw material; nuclear reactor; refining; processing; reprocessing; internationally regulated thing. Any person who is going to engage in refining businesses other than the Power Reactor and Nuclear Fuel Development Corporation shall get the special designation by the Prime Minister and the Minister of International Trade Industry. Any person who is going to engage in processing businesses shall get the particular admission of the Prime Minister. Any person who is going to establish reactors shall get the particular admission of the Prime Minister, The Minister of International Trade and Industry or the Minister of Transportation according to the kinds of specified reactors, respectively. Any person who is going to engage in reprocessing businesses other than the Power Reactor and Nuclear Fuel Development Corporation and the Japan Atomic Energy Research Institute shall get the special designation by the Prime Minister. The employment of nuclear fuel materials and internationally regulated things is defined in detail. (Okada, K.)

  18. The physical protection of nuclear material

    International Nuclear Information System (INIS)

    1989-12-01

    A Technical Committee on Physical Protection of Nuclear Material met in April-May 1989 to advise on the need to update the recommendations contained in document INFCIRC/225/Rev.1 and on any changes considered to be necessary. The Technical Committee indicated a number of such changes, reflecting mainly: the international consensus established in respect of the Convention on the Physical Protection of Nuclear Material; the experience gained since 1977; and a wish to give equal treatment to protection against the theft of nuclear material and protection against the sabotage of nuclear facilities. The recommendations presented in this IAEA document reflect a broad consensus among Member States on the requirements which should be met by systems for the physical protection of nuclear materials and facilities. 1 tab

  19. 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.

  20. Corrosion degradation of materials in nuclear reactors and its control

    International Nuclear Information System (INIS)

    Kain, Vivekanand

    2016-01-01

    As in every industry, nuclear industry also faces the challenge of corrosion degradation due to the exposure of the materials to the working environment. The aggressiveness of the environment is enhanced by the presence of radiation and high temperature and high-pressure environment. Radiation has influence on both the materials (changes in microstructure and microchemistry) and the aqueous environment (radiolysis producing oxidizing conditions). A survey of all the light water reactors in the world showed that stress corrosion cracking (SCC) and flow accelerated corrosion (FAC) account for more than two third of all the corrosion degradation cases. This paper visits these two forms of corrosion in nuclear power plants and illustrates cases from Indian nuclear power plants. Remedial measures against these two forms of corrosion that are possible to be employed and the actual measures employed in Indian nuclear power plants are discussed. Key features of SCC in different types of nuclear power plants are discussed. Main reasons for irradiation assisted stress corrosion cracking (IASCC) are presented and discussed. The signature patterns of single and dual phase FAC captured from components replaced from Indian nuclear power plants are presented. The development of a correlation between the scallop size and rate of single phase FAC - based on the database developed in Indian nuclear power plants is presented. Based on these two forms of degradation in nuclear reactors, design of materials that would resist these forms of degradation is presented. (author)

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

    International Nuclear Information System (INIS)

    Holzemer, Michael; Carvo, Alan

    2012-01-01

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

  2. Report of the international forum on nuclear energy, nuclear non-proliferation and nuclear security. Measures to ensure nuclear non-proliferation and nuclear security for the back end of nuclear fuel cycle and regional cooperation in Asia

    International Nuclear Information System (INIS)

    Tazaki, Makiko; Yamamura, Tsukasa; Suzuki, Mitsutoshi; Kuno, Yusuke; Mochiji, Toshiro

    2013-03-01

    The Japan Atomic Energy Agency (JAEA) held 'International Forum on Nuclear Energy, Nuclear Non-proliferation and Nuclear Security - Measures to ensure nuclear non-proliferation and nuclear security for the back end of nuclear fuel cycle and regional cooperation in Asia-' on 12 and 13 December 2012, co-hosted by the Japan Institute of International Affairs (JIIA) and School of Engineering, The University of Tokyo. In the forum, keynote speakers from Japan, International Atomic Energy Agency (IAEA), the U.S., France and Republic of Korea (ROK), respectively explained their efforts regarding peaceful use of nuclear energy and nuclear non-proliferation. In two panel discussions, entitled 'Measures to ensure nuclear non-proliferation and nuclear security of nuclear fuel cycle back end' and 'Measures to ensure nuclear non-proliferation and nuclear security for nuclear energy use in the Asian region and a multilateral cooperative framework', active discussions were made among panelists from Japan, IAEA, the U.S., France, ROK, Russia and Kazakhstan. This report includes abstracts of keynote speeches, summaries of two panel discussions and materials of the presentations in the forum. The editors take full responsibility for the wording and content of this report except presentation materials. (author)

  3. Study on interface between nuclear material accounting system and national nuclear forensic library

    International Nuclear Information System (INIS)

    Jeong, Yonhong; Han, Jae-Jun; Chang, Sunyoung; Shim, Hye-Won; Ahn, Seungho

    2016-01-01

    The implementation of nuclear forensics requires physical, chemical and radiological characteristics with transport history to unravel properties of seized nuclear materials. For timely assessment provided in the ITWG guideline, development of national response system (e.g., national nuclear forensic library) is strongly recommended. Nuclear material accounting is essential to obtain basic data in the nuclear forensic implementation phase from the perspective of nuclear non-proliferation related to the IAEA Safeguards and nuclear security. In this study, the nuclear material accounting reports were chosen due to its well-established procedure, and reviewed how to efficiently utilize the existing material accounting system to the nuclear forensic implementation phase In conclusion, limits and improvements in implementing the nuclear forensics were discussed. This study reviewed how to utilize the existing material accounting system for implementing nuclear forensics. Concerning item counting facility, nuclear material properties can be obtained based on nuclear material accounting information. Nuclear fuel assembly data being reported for the IAEA Safeguards can be utilized as unique identifier within the back-end fuel cycle. Depending upon the compulsory accountability report period, there exist time gaps. If national capabilities ensure that history information within the front-end nuclear fuel cycle is traceable particularly for the bulk handling facility, the entire cycle of national nuclear fuel would be managed in the framework of developing a national nuclear forensic library

  4. Study on interface between nuclear material accounting system and national nuclear forensic library

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Yonhong; Han, Jae-Jun; Chang, Sunyoung; Shim, Hye-Won; Ahn, Seungho [Korea Institute of Nuclear Non-proliferation and Control, Daejeon (Korea, Republic of)

    2016-10-15

    The implementation of nuclear forensics requires physical, chemical and radiological characteristics with transport history to unravel properties of seized nuclear materials. For timely assessment provided in the ITWG guideline, development of national response system (e.g., national nuclear forensic library) is strongly recommended. Nuclear material accounting is essential to obtain basic data in the nuclear forensic implementation phase from the perspective of nuclear non-proliferation related to the IAEA Safeguards and nuclear security. In this study, the nuclear material accounting reports were chosen due to its well-established procedure, and reviewed how to efficiently utilize the existing material accounting system to the nuclear forensic implementation phase In conclusion, limits and improvements in implementing the nuclear forensics were discussed. This study reviewed how to utilize the existing material accounting system for implementing nuclear forensics. Concerning item counting facility, nuclear material properties can be obtained based on nuclear material accounting information. Nuclear fuel assembly data being reported for the IAEA Safeguards can be utilized as unique identifier within the back-end fuel cycle. Depending upon the compulsory accountability report period, there exist time gaps. If national capabilities ensure that history information within the front-end nuclear fuel cycle is traceable particularly for the bulk handling facility, the entire cycle of national nuclear fuel would be managed in the framework of developing a national nuclear forensic library.

  5. Study of nuclear material accounting

    International Nuclear Information System (INIS)

    Ruderman, H.

    1977-01-01

    The implications of deliberate diversion of nuclear materials on materials accounting, the validity of the MUF concept to establish assurance concerning the possible diversion of special nuclear materials, and an economic analysis to permit cost comparison of varying the inventory frequency are being studied. An inventory cost model, the statistical hypothesis testing approach, the game theoretic approach, and analysis of generic plants are considered

  6. Action to counter illegal trafficking in nuclear materials in the northern region

    International Nuclear Information System (INIS)

    Reistad, O.; Maerli, M.

    1998-01-01

    Norway has not traditionally maintained any defence against smuggling of nuclear material. The 1993/94 report to Parliament on nuclear activities in areas adjacent to Norway mentioned the risk of such smuggling in the context of non-proliferation. In the light of this perceived risk a contact group was established with representatives from the Norwegian customs administration, police, armed forces and National Protection Authority. The group today has responsibility for the introduction of countermeasures against nuclear material smuggling in Norway. Another measure was establishment of Norwegian measurement facilities to combat smuggling of nuclear material. There arrangements are based on three lines of defence. The first will typically be the individual officer, the second, the special staff deployed following warnings or other indicators of smuggling, and the third would be any laboratory examination of specimens carried out in Norway or abroad

  7. Nuclear material control in Spain

    International Nuclear Information System (INIS)

    Velilla, A.

    1988-01-01

    A general view about the safeguards activities in Spain is presented. The national system of accounting for and control of nuclear materials is described. The safeguards agreements signed by Spain are presented and the facilities and nuclear materials under these agreements are listed. (E.G.) [pt

  8. Automated nuclear materials accounting

    International Nuclear Information System (INIS)

    Pacak, P.; Moravec, J.

    1982-01-01

    An automated state system of accounting for nuclear materials data was established in Czechoslovakia in 1979. A file was compiled of 12 programs in the PL/1 language. The file is divided into four groups according to logical associations, namely programs for data input and checking, programs for handling the basic data file, programs for report outputs in the form of worksheets and magnetic tape records, and programs for book inventory listing, document inventory handling and materials balance listing. A similar automated system of nuclear fuel inventory for a light water reactor was introduced for internal purposes in the Institute of Nuclear Research (UJV). (H.S.)

  9. New materials in nuclear fusion reactors

    International Nuclear Information System (INIS)

    Iwata, Shuichi

    1988-01-01

    In the autumn of 1987, the critical condition was attained in the JET in Europe and Japanese JT-60, thus the first subject in the physical verification of nuclear fusion reactors was resolved, and the challenge to the next attainment of self ignition condition started. As the development process of nuclear fusion reactors, there are the steps of engineering, economical and social verifications after this physical verification, and in respective steps, there are the critical problems related to materials, therefore the development of new materials must be advanced. The condition of using nuclear fusion reactors is characterized by high fluence, high thermal flux and strong magnetic field, and under such extreme condition, the microscopic structures of materials change, and they behave much differently from usual case. The subjects of material development for nuclear fusion reactors, the material data base being built up, the materials for facing plasma and high thermal flux, first walls, blanket structures, electric insulators and others are described. The serious effect of irradiation and the rate of defect inducement must be taken in consideration in the structural materials for nuclear fusion reactors. (Kako, I.)

  10. Regulations concerning the fabricating business of nuclear fuel materials

    International Nuclear Information System (INIS)

    1979-01-01

    The regulations are entirely revised under the law for the regulations of nuclear materials, nuclear fuel materials and reactors and provisions concerning the fabricating business in the order for execution of the law. Basic concepts and terms are defined, such as: exposure dose; accumulative dose; controlled area; inspected surrounding area; employee and radioactive waste. The application for permission of the fabricating business shall include: location of processing facilities; structure of building structure and equipment of chemical processing facilities; molding facilities; structure and equipment of covering and assembling facilities, storage facilities of nuclear fuel materials and disposal facilities of radioactive waste, etc. Records shall be made and kept for particular periods in each works and place of enterprise on inspection of processing facilities, control of dose, operation, maintenance, accident of processing facilities and weather. Specified measures shall be taken in controlled area and inspected surrounding area to restrict entrance. Measures shall be made not to exceed permissible exposure dose for employees defined by the Director General of Science and Technology Agency. Inspection and check up of processing facilities shall be carried on by employees more than once a day. Operation of processing facilities, transportation in the works and enterprise, storage, disposal, safety securing, report and measures in dangerous situations, etc. are in detail prescribed. (Okada, K.)

  11. The physical protection of nuclear material and nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-06-01

    The latest review (1993) of this document was of limited scope and resulted in changes to the text of INFCIRC/225/Rev.2 designed to make the categorization table in that document consistent with the categorization table contained in the Convention on Physical Protection of Nuclear Materials. Consequently, a comprehensive review of INFCIRC/225 has not been conducted since 1989. Consequently, a meeting of national experts was convened from 2-5 June 1998 and from 27-29 October 1998 for a thorough review of INFCIRC/225/Rev.3. The revised document reflects the recommendations of the national experts to improve the structure and clarity of the document and to take account of improved technology and current international and national practices. In particular, a chapter has been added which provides specific recommendations related to sabotage of nuclear facilities and nuclear material. As a result of this addition, the title has been changed to 'The Physical Protection of Nuclear Material and Nuclear Facilities'. The recommendations presented in this IAEA document reflect a broad consensus among Member States on the requirements which should be met by systems for the physical protection of nuclear materials and facilities. It is hoped that they will provide helpful guidance for Member States.

  12. The physical protection of nuclear material and nuclear facilities

    International Nuclear Information System (INIS)

    1999-06-01

    The latest review (1993) of this document was of limited scope and resulted in changes to the text of INFCIRC/225/Rev.2 designed to make the categorization table in that document consistent with the categorization table contained in the Convention on Physical Protection of Nuclear Materials. Consequently, a comprehensive review of INFCIRC/225 has not been conducted since 1989. Consequently, a meeting of national experts was convened from 2-5 June 1998 and from 27-29 October 1998 for a thorough review of INFCIRC/225/Rev.3. The revised document reflects the recommendations of the national experts to improve the structure and clarity of the document and to take account of improved technology and current international and national practices. In particular, a chapter has been added which provides specific recommendations related to sabotage of nuclear facilities and nuclear material. As a result of this addition, the title has been changed to 'The Physical Protection of Nuclear Material and Nuclear Facilities'. The recommendations presented in this IAEA document reflect a broad consensus among Member States on the requirements which should be met by systems for the physical protection of nuclear materials and facilities. It is hoped that they will provide helpful guidance for Member States

  13. NUMATH: a nuclear-material-holdup estimator for unit operations and chemical processes

    International Nuclear Information System (INIS)

    Krichinsky, A.M.

    1981-01-01

    A computer program, NUMATH (Nuclear Material Holdup Estimator), has been developed to permit inventory estimation in vessels involved in unit operations and chemical processes. This program has been implemented in an operating nuclear fuel processing plant. NUMATH's purpose is to provide steady-state composition estimates for material residing in process vessels until representative samples can be obtained and chemical analyses can be performed. Since these compositions are used for inventory estimation, the results are determined for and cataloged in container-oriented files. The estimated compositions represent material collected in applicable vessels-including consideration for material previously acknowledged in these vessels. The program utilizes process measurements and simple material balance models to estimate material holdups and distribution within unit operations. During simulated run testing, NUMATH-estimated inventories typically produced material balances within 7% of the associated measured material balances for uranium and within 16% of the associated, measured material balance for thorium during steady-state process operation

  14. Graphite materials for nuclear reactors

    International Nuclear Information System (INIS)

    Oku, Tatsuo

    1991-01-01

    Graphite materials have been used in the nuclear fission reactors from the beginning of the reactor development for the speed reduction and reflection of neutron. Graphite materials are used both as a moderator and as a reflector in the core of high temperature gas-cooled reactors, and both as a radiation shielding material and as a reflector in the surrounding of the core for the fast breeder reactor. On the other hand, graphite materials are being positively used as a first wall of plasma as it is known that low Z materials are useful for holding high temperature plasma in the nuclear fusion devices. In this paper the present status of the application of graphite materials to the nuclear fission reactors and fusion devices (reactors) is presented. In addition, a part of results on the related properties to the structural design and safety evaluation and results examined on the subjects that should be done in the future are also described. (author)

  15. Integrated Global Nuclear Materials Management Preliminary Concepts

    International Nuclear Information System (INIS)

    Jones, E; Dreicer, M.

    2006-01-01

    The world is at a turning point, moving away from the Cold War nuclear legacy towards a future global nuclear enterprise; and this presents a transformational challenge for nuclear materials management. Achieving safety and security during this transition is complicated by the diversified spectrum of threat 'players' that has greatly impacted nonproliferation, counterterrorism, and homeland security requirements. Rogue states and non-state actors no longer need self-contained national nuclear expertise, materials, and equipment due to availability from various sources in the nuclear market, thereby reducing the time, effort and cost for acquiring a nuclear weapon (i.e., manifestations of latency). The terrorist threat has changed the nature of military and national security requirements to protect these materials. An Integrated Global Nuclear Materials Management (IGNMM) approach would address the existing legacy nuclear materials and the evolution towards a nuclear energy future, while strengthening a regime to prevent nuclear weapon proliferation. In this paper, some preliminary concepts and studies of IGNMM will be presented. A systematic analysis of nuclear materials, activities, and controls can lead to a tractable, integrated global nuclear materials management architecture that can help remediate the past and manage the future. A systems approach is best suited to achieve multi-dimensional and interdependent solutions, including comprehensive, end-to-end capabilities; coordinated diverse elements for enhanced functionality with economy; and translation of goals/objectives or standards into locally optimized solutions. A risk-informed basis is excellent for evaluating system alternatives and performances, and it is especially appropriate for the security arena. Risk management strategies--such as defense-in-depth, diversity, and control quality--help to weave together various technologies and practices into a strong and robust security fabric. Effective

  16. LECI Department of Nuclear Materials

    International Nuclear Information System (INIS)

    2006-01-01

    The LECI is a 'hot' laboratory dedicated mostly to the characterization of irradiated materials. It has, however, limited activities on fuel, as a back up to the LECA STAR in Cadarache. The LECI belongs to the Section of Research on Irradiated Materials (Department of Nuclear Materials). The Department for Nuclear Materials (DMN) has for its missions: - to contribute, through theoretical and experimental investigations, to the development of knowledge in materials science in order to be able to predict the evolution of the material physical and mechanical properties under service conditions (irradiation, thermomechanical solicitations, influence of the environment,..); - to characterize the properties of the materials used in the nuclear industry in order to determine their performance and to be able to predict their life expectancy, in particular via modelling. These materials can be irradiated or not, and originate from surveillance programs, experimental neutron irradiations or simulated irradiations with charged particles; - to establish, maintain and make use of the databases generated by these data; - to propose new or optimized materials, satisfying future service conditions and extend the life or the competitiveness of the associated systems; - to establish constitutive laws and models for the materials in service, incidental, accidental and storage conditions, and contribute to the development of the associated design codes in order to support the safety argumentation of utilities and vendors; - to provide expertise on industrial components, in particular to investigate strain or rupture mechanisms and to offer leads for improvement. This document presents, first, the purpose of the LECI (Historical data, Strategy, I and K shielded cell lines (building 605), M shielded cell line (building 625), Authorized materials). Then, it presents the microscopy and irradiation damage studies laboratory of the Saclay centre (Building 605) Which belongs to the Nuclear

  17. Detection of smuggling of nuclear material covered by a legal transport of radioactive material

    International Nuclear Information System (INIS)

    Safar, J.; Zsigrai, J.; Tam, N.C.; Lakosi, L.

    2001-01-01

    Full text: One of the worst scenarios for detection of illicit trafficking of nuclear material is when a legal transport of radioactive material is used to cover the radiation of the smuggled uranium. Feasibility study was performed in the Institute of Isotopes and Surface Chemistry of the Chemical Research Centre of the Hungarian Academy of Sciences (hereinafter: Institute) in order to study the possible on site measurement techniques and approaches applicable in such cases. As the type A and type B packages always incorporate a feature such as a seal, in a realistic scenario the confiscated nuclear material is expected to be placed outside the package. The passive neutron emission of the uranium is negligible for a reasonable isotopic abundance therefore the feasibility study was concentrating on non-destructive, passive gamma- spectrometric methods. Possible application of Nal (diameter 40x40 mm 3 , large planar (15x15x3 mm 3 ) and a hemispheric CdZnTe (500 mm 3 , and high purity Germanium detectors was investigated. During the on site measurements portable electronics, mini multichannel analyzer, palmtop and/or notebook computer were used. The shielding material of the packages was lead or depleted uranium. The smuggled material was simulated by a package of reactor fuel pellets containing low enriched or natural uranium (materials confiscated in earlier cases) and standards containing low enriched uranium. During the supposed scenario the portal monitor provides an indication of an elevated level of the environmental radioactivity. Then the responsible (e.g. customs) officer investigate the vehicle by a hand-held survey meter in order to search for peaks in dose rates. If a peak was localized, which is different from the position of the legally transported package(s) the officer requests for the expertise of the designated institutes. The following model cases provided the basic conclusion: 1. The legal transport of the radioactive material was simulated by a

  18. The law for the regulations of nuclear source materials, nuclear fuel materials and reactors

    International Nuclear Information System (INIS)

    1978-01-01

    This law has following two purposes. At first, it exercises necessary controls concerning nuclear source material, nuclear fuel material and reactors in order to: (a) limit their uses to those for the peaceful purpose; (b) ensure planned uses of them; and (c) ensure the public safety by preventing accidents from their uses. Necessary controls are to be made concerning the refining, fabricating and reprocessing businesses, as well as the construction and operation of reactors. The second purpose of the law is to exercise necessary controls concerning internationally controlled material in order to execute the treaties and other international agreements on the research, development and use of atomic energy (the first chapter). In the second and following chapters the law prescribes controls for the persons who wish to carry on the refining and fabricating businesses, to construct and operate reactors, and to conduct the reprocessing business, as well as for those who use the internationally controlled material, respectively in separate chapters by the category of those businesses. For example, the controls to the person who wishes to construct and operate reactors are: (a) the permission of the business after the examination; (b) the examination and approval of the design and methods of construction prior to the construction; (c) the inspection of the facilities prior to their use; (d) periodic inspections of the facilities; (e) the establishment of requirements for safety measures and punishments to their violations. (Matsushima, A.)

  19. Development of methods for measuring materials nuclear characteristics, Phases, I, II, II and IV; Razvijanje metoda merenja nuklearnih karakteristika materijala, I, II, II i VI faza

    Energy Technology Data Exchange (ETDEWEB)

    Maglic, R [Boris Kidric Institute of Nuclear Sciences Vinca, Belgrade (Yugoslavia)

    1963-04-15

    This report contains the following phases of the project 'measurement of nuclear characteristics of reactor materials': nuclear performances of the neutron chopper; method for measuring total effective cross sections by transmission method on the chopper; review of methods for measuring activation cross sections; measurement of neutron spectra of the RA reactor and measurement of total effective cross section of gold by using the chopper.

  20. Central eastern Europe approach to the security over nuclear materials

    International Nuclear Information System (INIS)

    Smagala, G.

    2002-01-01

    Full text: This paper presents an overview of the national approaches to physical protection of nuclear materials in Central Eastern Europe (CEE), with an emphasis on Poland. Soviet influence in the past led to inadequate safety culture in nuclear activities and insufficient security of nuclear materials and facilities in the region. In the centralized economies all aspects of nuclear activities, including ownership of the nuclear facilities, were the responsibility of the state with no clear separation between regulating and promoting functions. During the last decade a significant progress has been made in the region to clean up the legacy of the past and to improve practices in physical protection of nuclear materials. The countries of Central Eastern Europe have had many similar deficiencies in nuclear field and problems to overcome, but cannot be viewed as a uniform block. There are local variations within the region in a size of nuclear activities, formulated respective regulations and adopted measures to secure nuclear materials and facilities. Nevertheless, all twelve nations, with nuclear reactors and without nuclear facilities, have joined the convention on the physical protection of nuclear material and most of them declare that they have followed the IAEA recommendations INFCIRC/225/Rev.4 to elaborate and implement their physical protection systems of nuclear materials and facilities. The largest request for an international advisory mission (IPPAS) to review states' physical protection systems and to address needs for improvement was received from the countries of Central Eastern Europe. Poland belongs to the beneficiaries where the IPPAS mission and later follow-up consultations resulted in physical protection upgrade of the research reactor under the IAEA/US/UK technical assistance project. A powerful incentive to the progress made in a number of CEE countries was the goal of accession to the European Union. The physical protection of nuclear

  1. A study on strengthening measures of non-proliferation regime through the export control system of sensitive materials, equipment and technology related to nuclear activities

    International Nuclear Information System (INIS)

    Kikuchi, Masahiro; Kurosawa, Mitsuru; Komizo, Yasuyoshi

    2004-01-01

    The strengthened safeguards caused from safeguards experiences to Iraq and DPRK leads to the expansion of the IAEA's activities for verification of all nuclear activities as well as verification of nuclear material in the States. The purpose of the activities, of course, includes detection of undeclared exports and imports of specified equipment and non-nuclear material. The Additional Protocol to the agreements between States and the IAEA for the application of safeguards requires to the States to declare the exports and imports information regarding specified equipment and non-nuclear material corresponding to the export control list that is established by the nuclear suppliers group. The Additional Protocol also insists the IAEA's right to access to the location identified by the State to resolve a question related to the declarations. Recently, the IAEA detected the black market group of the sensitive materials, equipment and technologies relevant to the nuclear proliferation through the safeguards activities to Iran and Libya. International community stated deeply concerns to the indecent facts. This paper would discuss and propose the supplemental strengthening measures of non-proliferation regime by effective combination of the safeguards activities under additional protocol and the export control regime. (author)

  2. Material degradation - a nuclear utility's view

    International Nuclear Information System (INIS)

    Spekkens, P.

    2007-01-01

    Degradation of nuclear plant materials has been responsible for major costs and unit outage time. As such, nuclear utilities are important end users of the information produced by R and D on material degradation. This plenary describes the significance of material degradation for the nuclear utilities, and how utilities use information about material degradation in their short, medium and long term planning activities. Utilities invest in R and D programs to assist them in their business objective of operating safely, reliably and cost competitively. Material degradation impacts all three of these business drivers. Utilities make decisions on life cycle planning, unit refurbishment and 'new build' projects on the basis of their understanding of the behaviour of a variety of materials in a broad range of environments. The R and D being carried out today will determine the future business success of the nuclear utilities. The R and D program needs to be broadly based to include a range of materials, environments and time-frames, particularly any new materials proposed for use in new units. The R and D community needs to help the utility managers make choices that will result in an optimized materials R and D program

  3. Conformity Assessment in Nuclear Material and Environmental Sample Analysis

    International Nuclear Information System (INIS)

    Aregbe, Y.; Jakopic, R.; Richter, S.; Venchiarutti, C.

    2015-01-01

    Safeguards conclusions are based to a large extent on comparison of measurement results between operator and safeguards laboratories. Measurement results must state traceability and uncertainties to be comparable. Recent workshops held at the IAEA and in the frame of the European Safeguards Research and Development Association (ESARDA), reviewed different approaches for Nuclear Material Balance Evaluation (MBE). Among those, the ''bottom-up'' approach requires assessment of operators and safeguards laboratories measurement systems and capabilities. Therefore, inter-laboratory comparisons (ILCs) with independent reference values provided for decades by JRC-IRMM, CEA/CETAMA and US DOE are instrumental to shed light on the current state of practice in measurements of nuclear material and environmental swipe samples. Participating laboratories are requested to report the measurement results with associated uncertainties, and have the possibility to benchmark those results against independent and traceable reference values. The measurement capability of both the IAEA Network of Analytical Laboratories (NWAL) and the nuclear operator's analytical services participating in ILCs can be assessed against the independent reference values as well as against internationally agreed quality goals, in compliance with ISO 13528:2005. The quality goals for nuclear material analysis are the relative combined standard uncertainties listed in the ITV2010. Concerning environmental swipe sample analysis, the IAEA defined measurement quality goals applied in conformity assessment. The paper reports examples from relevant inter-laboratory comparisons, looking at laboratory performance according to the purpose of the measurement and the possible use of the result in line with the IUPAC International Harmonized Protocol. Tendencies of laboratories to either overestimate and/or underestimate uncertainties are discussed using straightforward graphical tools to evaluate

  4. Physical Protection of Nuclear Material and Nuclear Facilities (Implementation of INFCIRC/225/Revision 5). Implementing Guide

    International Nuclear Information System (INIS)

    2018-01-01

    This publication is the lead Implementing Guide in a suite of guidance on implementing the Nuclear Security Recommendations on Physical Protection of Nuclear Material and Nuclear Facilities (INFCIRC/225/Revision 5), IAEA Nuclear Security Series No. 13. It provides guidance and suggestions to assist States and their competent authorities in establishing, strengthening and sustaining their national physical protection regime and implementing the associated systems and measures, including operators’ physical protection systems. The structure of this publication is as follows. After this introduction, Section 2 describes the objectives of physical protection and the overall approach to managing the risks of the unauthorized removal of nuclear material and the sabotage of nuclear facilities. Section 3 provides guidance for the State and its competent authorities on the physical protection elements of the nuclear security regime; this guidance is based on the fundamental principles set out in the Recommendations publication. Section 4 provides guidance on the operator’s physical protection system and describes a systematic, integrated approach. Appendix I gives an annotated outline of the typical contents of an operator’s security plan. Appendix II provides similar guidance for the contingency plan. Appendix III provides a description of nuclear material aggregation that can be used to categorize nuclear material and determine the appropriate level of protection against unauthorized removal. Appendix IV presents a table of paragraph cross-references between the Recommendations publication and this Implementing Guide.

  5. A system of nuclear material accountancy in the JAERI

    International Nuclear Information System (INIS)

    Kase, Toshio; Nishizawa, Satoshi; Takahashi, Yoshindo

    1983-05-01

    Pursuant to the domestic law and regulations revised in 1978 as to be conformed to the requirements specified in the Safeguards Agreement under the Non-Proliferation Treaty (NPT), the JAERI's system of nuclear material accountancy has been effectively developed. The system of accountancy in the JAERI is based on the information treatment by the computer. The data of nuclear material are retained batchwisely together with their complicate history reflected the inventory changes and other transactions. The reports represented these data are prepared and submitted to the IAEA through the Government every month. The inspections are frequently conducted to the JAERI to verify the material appeared in the reports. Item counting, item identification and non-destructive assay technique are brought to the verification. In some cases, seals of the Government and the IAEA are applied to the nuclear material at the inspections, as their containment measures. The surveillance camera is also installed in the facility to look whole view of reactor room and spent fuel pond. In this paper, the general safeguards application and its corresponding accountancy system on JAERI's nuclear facility are described. (author)

  6. Control of Nuclear Material in Republic of Croatia

    International Nuclear Information System (INIS)

    Cizmek, A.; Medakovic, S.; Prah, M.; Novosel, N.

    2008-01-01

    State Office for Nuclear Safety (SONS) is established based on 'Nuclear Safety Act' (Official Gazette No. 173/2003) as an independent state organization responsible for all questions in connection with safe use of nuclear energy and technology, for expert matters of preparedness in the case of nuclear emergency, as well as for international co-operation in these fields (regulatory body). In the second half of year 2006, stationary detection systems for nuclear and other radioactive materials were installed on Border Crossing Bregana, Croatia. Yantar 2U, which is the commercial name of the system, is integrated automatic system capable of detection of nuclear and other radioactive materials prepared for fixed-site customs applications (Russian origin). Installed system contains portal monitors, camera, communication lines and communication boxes and server. Two fully functional separate systems has been installed on BC Bregana, one on truck entrance and another one on car entrance. In this article the operational experience of installed system is presented. This includes statistical analysis of recorded alarms, evaluation of procedures for operational stuff and maintenance and typical malfunction experience, as well as some of the recommendation for future use of detection systems. Ordinance on the control of nuclear material and special equipment (Official Gazette No. 15/08) lays down the list of nuclear materials and special equipment as well as the list of other activities related to the production of special equipment and non-nuclear materials; the contents of the declaration of intent form for export/import of goods, the form for notifying export/import of goods, the form for notifying transport of nuclear material, the form for notifying the activity related to producing of special equipment and non-nuclear material, as well as of the form of the report on nuclear material balance in the user's material balance area. This Ordinance lays down the method of

  7. Conceptual design of a system for nuclear material control in a research centre according to the IAEA safeguards requirements

    International Nuclear Information System (INIS)

    Bueker, H.; Kotte, U.; Stein, G.

    1976-01-01

    In comparison with other facilities handling nuclear material, a nuclear research centre is characterized by a wider spectrum of operations. This requires a number of installations within the centre such as research reactors, critical assemblies, research institutes and central departments, operating, in general, independently of each other. Nuclear material is stored and processed in small quantities and in different chemical and physical configurations within prescribed license areas. The conceptual design of a new system for nuclear material control in a research centre has to consider the operator's and IAEA's safeguards requirements. Using the example of the Juelich Nuclear Research Centre in the Federal Republic of Germany, these requirements are being examined in conjunction with the specified peculiarities of a nuclear research centre. Following this, a division of the research centre into material balance areas and key measurement points is being proposed, based on the existing facilities and licence areas. The essential characteristic of the concept is a far-reaching displayability of the inventory and flow of nuclear material. The availability of information is based on differentiated material accountancy in conjunction with adequate measurement of nuclear material data. For data processing and generation of data, a computerized record and report system is to be provided as well as a central measurement system. The design of an integrated accountancy system with a central computer and remote terminals is described; various measuring appliances, now being developed or tested, for the non-destructive assay of nuclear material are specified. The functions of a central department for nuclear material management for operating these systems are discussed and the planned verification of nuclear material in the different material balance areas illustrated. On applying the measures described in this paper, the conceptual design of a system for nuclear material

  8. Calculations to support design of a nuclear material tracking system

    International Nuclear Information System (INIS)

    Carter, L.L.; Eggers, R.F.; Williams, T.L.

    1991-01-01

    The Westinghouse Hanford Company is developing a nuclear material tracking system called NTRAK for the US Department of Energy at the Savannah River site. The NTRAK system is designed to determine the position and approximate magnitude of packages of special nuclear material (SNM) moving through a nuclear plant. The NTRAK accomplishes this by using special assemblies of detectors called modules to measure the gamma radiation emitted by the SNM. After measurement, raw data are processed to determine the direction to and position of the gamma-ray source. In order for the NTRAK method of SNM tracking to work, the gamma-ray signal at the detector modules must be at least four standard deviations above background. This paper addresses the use of the Monte Carlo computer code for neutron and photon transport (MCNP) to (a) predict the radiation emitted by plutonium oxide sources and (b) predict the counting rate of NaI detectors measuring those sources

  9. Nuclear material control in Brazil

    International Nuclear Information System (INIS)

    Marzo, M.A.S.; Iskin, M.C.L.; Palhares, L.C.; Almeida, S.G. de.

    1988-01-01

    A general view about the safeguards activities in Brazil is presented. The national system of accounting for and control of nuclear materials is described. The safeguards agreements signed by Brazil are presented, the facilities and nuclear material under these agreements are listed, and the dificulties on the pratical implementation are discussed. (E.G.) [pt

  10. Filter Measurement System for Nuclear Material Storage Canisters. End of Year Report FY 2013

    Energy Technology Data Exchange (ETDEWEB)

    Moore, Murray E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Reeves, Kirk P. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-02-03

    A test system has been developed at Los Alamos National Laboratory to measure the aerosol collection efficiency of filters in the lids of storage canisters for special nuclear materials. Two FTS (filter test system) devices have been constructed; one will be used in the LANL TA-55 facility with lids from canisters that have stored nuclear material. The other FTS device will be used in TA-3 at the Radiation Protection Division’s Aerosol Engineering Facility. The TA-3 system will have an expanded analytical capability, compared to the TA-55 system that will be used for operational performance testing. The LANL FTS is intended to be automatic in operation, with independent instrument checks for each system component. The FTS has been described in a complete P&ID (piping and instrumentation diagram) sketch, included in this report. The TA-3 FTS system is currently in a proof-of-concept status, and TA-55 FTS is a production-quality prototype. The LANL specification for (Hagan and SAVY) storage canisters requires the filter shall “capture greater than 99.97% of 0.45-micron mean diameter dioctyl phthalate (DOP) aerosol at the rated flow with a DOP concentration of 65±15 micrograms per liter”. The percent penetration (PEN%) and pressure drop (DP) of fifteen (15) Hagan canister lids were measured by NFT Inc. (Golden, CO) over a period of time, starting in the year 2002. The Los Alamos FTS measured these quantities on June 21, 2013 and on Oct. 30, 2013. The LANL(6-21-2013) results did not statistically match the NFT Inc. data, and the LANL FTS system was re-evaluated, and the aerosol generator was replaced and the air flow measurement method was corrected. The subsequent LANL(10-30-2013) tests indicate that the PEN% results are statistically identical to the NFT Inc. results. The LANL(10-30-2013) pressure drop measurements are closer to the NFT Inc. data, but future work will be investigated. An operating procedure for the FTS (filter test system) was written, and

  11. Radiation Effects in Nuclear Waste Materials

    International Nuclear Information System (INIS)

    Weber, William J.; Wang, Lumin; Hess, Nancy J.; Icenhower, Jonathan P.; Thevuthasan, Suntharampillai

    2003-01-01

    The objective of this project is to develop a fundamental understanding of radiation effects in glasses and ceramics, as well as the influence of solid-state radiation effects on aqueous dissolution kinetics, which may impact the performance of nuclear waste forms and stabilized nuclear materials. This work provides the underpinning science to develop improved glass and ceramic waste forms for the immobilization and disposition of high-level tank waste, excess plutonium, plutonium residues and scrap, other actinides, and other nuclear waste streams. Furthermore, this work is developing develop predictive models for the performance of nuclear waste forms and stabilized nuclear materials. Thus, the research performed under this project has significant implications for the immobilization of High-Level Waste (HLW) and Nuclear Materials, two mission areas within the Office of Environmental Management (EM). With regard to the HLW mission, this research will lead to improved understanding of radiation-induced degradation mechanisms and their effects on dissolution kinetics, as well as development of predictive models for waste form performance. In the Nuclear Materials mission, this research will lead to improvements in the understanding of radiation effects on the chemical and structural properties of materials for the stabilization and long-term storage of plutonium, highly-enriched uranium, and other actinides. The research uses plutonium incorporation, ion-beam irradiation, and electron-beam irradiation to simulate the effects of alpha decay and beta decay on relevant glasses and ceramics. The research under this project has the potential to result in improved glass and ceramic materials for the stabilization and immobilization of high-level tank waste, plutonium residues and scraps, surplus weapons plutonium, highly-enriched uranium, other actinides, and other radioactive materials

  12. Radiation Effects in Nuclear Waste Materials

    International Nuclear Information System (INIS)

    Weber, William J.

    2005-01-01

    The objective of this project is to develop a fundamental understanding of radiation effects in glasses and ceramics, as well as the influence of solid-state radiation effects on aqueous dissolution kinetics, which may impact the performance of nuclear waste forms and stabilized nuclear materials. This work provides the underpinning science to develop improved glass and ceramic waste forms for the immobilization and disposition of high-level tank waste, excess plutonium, plutonium residues and scrap, other actinides, and other nuclear waste streams. Furthermore, this work is developing develop predictive models for the performance of nuclear waste forms and stabilized nuclear materials. Thus, the research performed under this project has significant implications for the immobilization of High-Level Waste (HLW) and Nuclear Materials, two mission areas within the Office of Environmental Management (EM). With regard to the HLW mission, this research will lead to improved understanding of radiation-induced degradation mechanisms and their effects on dissolution kinetics, as well as development of predictive models for waste form performance. In the Nuclear Materials mission, this research will lead to improvements in the understanding of radiation effects on the chemical and structural properties of materials for the stabilization and long-term storage of plutonium, highly-enriched uranium, and other actinides. The research uses plutonium incorporation, ion-beam irradiation, and electron-beam irradiation to simulate the effects of alpha decay and beta decay on relevant glasses and ceramics. The research under this project has the potential to result in improved glass and ceramic materials for the stabilization and immobilization of high-level tank waste, plutonium residues and scraps, surplus weapons plutonium, highly-enriched uranium, other actinides, and other radioactive materials

  13. Illegal handling of radioactive and nuclear materials. Threats and suggestions for measures

    International Nuclear Information System (INIS)

    Oliver, Lena; Melin, Lena; Prawitz, Jan; Ringbom, Anders; Sandstroem, Bjoern; Wigg, Lars; Wirstam, Jens

    2004-01-01

    This project deals with threats from smuggling or other illegal transportation of radioactive or nuclear materials across the borders to Sweden, and with the security of handling such materials in Sweden. The project has included studies of relevant documentation; visits and interviews at industries, hospitals, research institutes and military institutions in Sweden that handle radioactive materials; a pilot study at the Stockholm freeport, where equipment for detection of radioactive materials has been tested for six months; an analysis of incidents reported to the IAEA database; and an analysis of Swedish incidents. The following conclusions are drawn: Stricter rules regarding the physical protection of radiation sources and radioactive materials should be implemented in Sweden. The recommendations recently issued by IAEA should serve as a point of departure for working out such rules

  14. In core instrumentation for online nuclear heating measurements of material testing reactor

    International Nuclear Information System (INIS)

    Reynard, C.; Andre, J.; Brun, J.; Carette, M.; Janulyte, A.; Merroun, O.; Zerega, Y.; Lyoussi, A.; Bignan, G.; Chauvin, J-P.; Fourmentel, D.; Glayse, W.; Gonnier, C.; Guimbal, P.; Iracane, D.; Villard, J.-F.

    2010-01-01

    The present work focuses on nuclear heating. This work belongs to a new advanced research program called IN-CORE which means 'Instrumentation for Nuclear radiations and Calorimetry Online in REactor' between the LCP (University of Provence-CNRS) and the CEA (French Atomic Energy Commission) - Jules Horowitz Reactor (JHR) program. This program started in September 2009 and is dedicated to the conception and the design of an innovative mobile experimental device coupling several sensors and ray detectors for on line measurements of relevant physical parameters (photonic heating, neutronic flux ...) and for an accurate parametric mapping of experimental channels in the JHR Core. The work presented below is the first step of this program and concerns a brief state of the art related to measurement methods of nuclear heating phenomena in research reactor in general and MTR in particular. A special care is given to gamma heating measurements. A first part deals with numerical codes and models. The second one presents instrumentation divided into various kinds of sensor such as calorimeter measurements and gamma ionization chamber measurements. Their basic principles, characteristics such as metrological parameters, operating mode, disadvantages/advantages, ... are discussed. (author)

  15. Nuclear materials transport worldwide

    International Nuclear Information System (INIS)

    Stellpflug, J.

    1987-01-01

    This Greenpeace report shows: nuclear materials transport is an extremely hazardous business. There is no safe protection against accidents, kidnapping, or sabotage. Any moment of a day, at any place, a nuclear transport accident may bring the world to disaster, releasing plutonium or radioactive fission products to the environment. Such an event is not less probable than the MCA at Chernobyl. The author of the book in hand follows the secret track of radioactive materials around the world, from uranium mines to the nuclear power plants, from reprocessing facilities to the waste repositories. He explores the routes of transport and the risks involved, he gives the names of transport firms and discloses incidents and carelessness, tells about damaged waste drums and plutonium that 'disappeared'. He also tells about worldwide, organised resistance to such nuclear transports, explaining the Greenpeace missions on the open sea, or the 'day X' operation at the Gorleben site, informing the reader about protests and actions for a world freed from the threat of nuclear energy. (orig./HP) [de

  16. Nuclear data needs for material analysis

    International Nuclear Information System (INIS)

    Molnar, Gabor L.

    2001-01-01

    Nuclear data for material analysis using neutron-based methods are examined. Besides a critical review of the available data, emphasis is given to emerging application areas and new experimental techniques. Neutron scattering and reaction data, as well as decay data for delayed and prompt gamma activation analysis are all discussed in detail. Conclusions are formed concerning the need of new measurement, calculation, evaluation and dissemination activities. (author)

  17. The criticality check and its applicability for nuclear material accounting

    International Nuclear Information System (INIS)

    Sanchez Espinoza, V.H.; Adam, E.; Knorr, J.

    1988-01-01

    Different procedures are used by the realization of nuclear material check by the IAEA. The criticality check belongs to these methods and it appropriates especially to verification of the nuclear material inventory of reactors. General aspects of the applicability of this check procedure are formulated and application criteria are deduced. By the example of solid-moderated homogeneous zero-power reactors it is demonstrated the unsecurity which is to be reckoned by applying the criticality check. Finally a possibility for the reduction of errors in core material determination by additional measuring methods without questioning the criticality check method is presented. (author)

  18. Active Interrogation using Photofission Technique for Nuclear Materials Control and Accountability

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Haori [Oregon State Univ., Corvallis, OR (United States)

    2016-03-31

    Innovative systems with increased sensitivity and resolution are in great demand to detect diversion and to prevent misuse in support of nuclear materials management for the U.S. fuel cycle. Nuclear fission is the most important multiplicative process involved in non-destructive active interrogation. This process produces the most easily recognizable signature for nuclear materials. In addition to thermal or high-energy neutrons, high-energy gamma rays can also excite a nucleus and cause fission through a process known as photofission. Electron linear accelerators (linacs) are widely used as the interrogating photon sources for inspection methods involving photofission technique. After photofission reactions, prompt signals are much stronger than the delayed signals, but it is difficult to quantify them in practical measurements. Delayed signals are easily distinguishable from the interrogating radiation. Linac-based, advanced inspection techniques utilizing the delayed signals after photofission have been extensively studied for homeland security applications. Previous research also showed that a unique delayed gamma ray energy spectrum exists for each fissionable isotope. In this work, high-energy delayed γ-rays were demonstrated to be signatures for detection, identification, and quantification of special nuclear materials. Such γ-rays were measured in between linac pulses using independent data acquisition systems. A list-mode system was developed to measure low-energy delayed γ-rays after irradiation. Photofission product yields of 238U and 239Pu were determined based on the measured delayed γ-ray spectra. The differential yields of delayed γ-rays were also proven to be able to discriminate nuclear from non-nuclear materials. The measurement outcomes were compared with Monte Carlo simulation results. It was demonstrated that the current available codes have capabilities and limitations in the simulation of photofission process. A two

  19. Active Interrogation using Photofission Technique for Nuclear Materials Control and Accountability

    International Nuclear Information System (INIS)

    Yang, Haori

    2016-01-01

    Innovative systems with increased sensitivity and resolution are in great demand to detect diversion and to prevent misuse in support of nuclear materials management for the U.S. fuel cycle. Nuclear fission is the most important multiplicative process involved in non-destructive active interrogation. This process produces the most easily recognizable signature for nuclear materials. In addition to thermal or high-energy neutrons, high-energy gamma rays can also excite a nucleus and cause fission through a process known as photofission. Electron linear accelerators (linacs) are widely used as the interrogating photon sources for inspection methods involving photofission technique. After photofission reactions, prompt signals are much stronger than the delayed signals, but it is difficult to quantify them in practical measurements. Delayed signals are easily distinguishable from the interrogating radiation. Linac-based, advanced inspection techniques utilizing the delayed signals after photofission have been extensively studied for homeland security applications. Previous research also showed that a unique delayed gamma ray energy spectrum exists for each fissionable isotope. In this work, high-energy delayed γ-rays were demonstrated to be signatures for detection, identification, and quantification of special nuclear materials. Such γ-rays were measured in between linac pulses using independent data acquisition systems. A list-mode system was developed to measure low-energy delayed γ-rays after irradiation. Photofission product yields of 238 U and 239 Pu were determined based on the measured delayed γ-ray spectra. The differential yields of delayed γ-rays were also proven to be able to discriminate nuclear from non-nuclear materials. The measurement outcomes were compared with Monte Carlo simulation results. It was demonstrated that the current available codes have capabilities and limitations in the simulation of photofission process. A two-fold approach was

  20. Semi-annual report on strategic special nuclear material inventory differences

    International Nuclear Information System (INIS)

    1984-07-01

    This fourteenth periodic semiannual report of Inventory Differences (ID) covers the last six months of fiscal year 1983 (April 1, 1983 through September 30, 1983), for the Department of Energy (DOE) and DOE contractor facilities possessing significant quantities of strategic special nuclear material (SSNM). Inventory Differences are expected in nuclear material processing and are not, in and of themselves, evidence of lost or stolen material. On the other hand, ID analysis provides valuable information on the effectiveness of the safeguards system's physical protection and material control measures as well as a check on the process controls and material management procedures. ID's outside safeguards control limits or involving a missing SSNM discrete item are investigated. If necessary, an operation may be shut down until an ID is resolved

  1. Nuclear materials for fission reactors

    International Nuclear Information System (INIS)

    Matzke, H.; Schumacher, G.

    1992-01-01

    This volume brings together 47 papers from scientists involved in the fabrication of new nuclear fuels, in basic research of nuclear materials, their application and technology as well as in computer codes and modelling of fuel behaviour. The main emphasis is on progress in the development of non -oxide fuels besides reporting advances in the more conventional oxide fuels. The two currently performed large reactor safety programmes CORA and PHEBUS-FP are described in invited lectures. The contributions review basic property measurements, as well as the present state of fuel performance modelling. The performance of today's nuclear fuel, hence UO 2 , at high burnup is also reviewed with particular emphasis on the recently observed phenomenon of grain subdivision in the cold part of the oxide fuel at high burnup, the so-called 'rim' effect. Similar phenomena can be simulated by ion implantation in order to better elucidate the underlying mechanism and reviews on high resolution electron microscopy provide further information. The papers will provide a useful treatise of views, ideas and new results for all those scientists and engineers involved in the specific questions of current nuclear waste management

  2. 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)

  3. Metabonomics for detection of nuclear materials processing

    International Nuclear Information System (INIS)

    Alam, Todd Michael; Luxon, Bruce A.; Neerathilingam, Muniasamy; Ansari, S.; Volk, David; Sarkar, S.; Alam, Mary Kathleen

    2010-01-01

    Tracking nuclear materials production and processing, particularly covert operations, is a key national security concern, given that nuclear materials processing can be a signature of nuclear weapons activities by US adversaries. Covert trafficking can also result in homeland security threats, most notably allowing terrorists to assemble devices such as dirty bombs. Existing methods depend on isotope analysis and do not necessarily detect chronic low-level exposure. In this project, indigenous organisms such as plants, small mammals, and bacteria are utilized as living sensors for the presence of chemicals used in nuclear materials processing. Such 'metabolic fingerprinting' (or 'metabonomics') employs nuclear magnetic resonance (NMR) spectroscopy to assess alterations in organismal metabolism provoked by the environmental presence of nuclear materials processing, for example the tributyl phosphate employed in the processing of spent reactor fuel rods to extract and purify uranium and plutonium for weaponization.

  4. Nuclear materials facility safety initiative

    International Nuclear Information System (INIS)

    Peddicord, K.L.; Nelson, P.; Roundhill, M.; Jardine, L.J.; Lazarev, L.; Moshkov, M.; Khromov, V.V.; Kruchkov, E.; Bolyatko, V.; Kazanskij, Yu.; Vorobeva, I.; Lash, T.R.; Newton, D.; Harris, B.

    2000-01-01

    Safety in any facility in the nuclear fuel cycle is a fundamental goal. However, it is recognized that, for example, should an accident occur in either the U.S. or Russia, the results could seriously delay joint activities to store and disposition weapons fissile materials in both countries. To address this, plans are underway jointly to develop a nuclear materials facility safety initiative. The focus of the initiative would be to share expertise which would lead in improvements in safety and safe practices in the nuclear fuel cycle.The program has two components. The first is a lab-to-lab initiative. The second involves university-to-university collaboration.The lab-to-lab and university-to-university programs will contribute to increased safety in facilities dealing with nuclear materials and related processes. These programs will support important bilateral initiatives, develop the next generation of scientists and engineers which will deal with these challenges, and foster the development of a safety culture

  5. Modernizing computerized nuclear material accounting systems

    International Nuclear Information System (INIS)

    Erkkila, B.H.; Claborn, J.

    1995-01-01

    DOE Orders and draft orders for nuclear material control and accountability address a complete material control and accountability (MC and A) program for all DOE contractors processing, using, or storing nuclear materials. A critical element of an MC and A program is the accounting system used to track and record all inventories of nuclear material and movements of materials in those inventories. Most DOE facilities use computerized accounting systems to facilitate the task of accounting for all their inventory of nuclear materials. Many facilities still use a mixture of a manual paper system with a computerized system. Also, facilities may use multiple systems to support information needed for MC and A. For real-time accounting it is desirable to implement a single integrated data base management system for a variety of users. In addition to accountability needs, waste management, material management, and production operations must be supported. Information in these systems can also support criticality safety and other safety issues. Modern networked microcomputers provide extensive processing and reporting capabilities that single mainframe computer systems struggle with. This paper describes an approach being developed at Los Alamos to address these problems

  6. Reducing nuclear danger through intergovernmental technical exchanges on nuclear materials safety management

    International Nuclear Information System (INIS)

    Jardine, L.J.; Peddicord, K.L.; Witmer, F.E.; Krumpe, P.F.; Lazarev, L.; Moshkov, M.

    1997-01-01

    The United States and Russia are dismantling nuclear weapons and generating hundreds of tons of excess plutonium and high enriched uranium fissile nuclear materials that require disposition. The U.S. Department of Energy and Russian Minatom organizations.are planning and implementing safe, secure storage and disposition operations for these materials in numerous facilities. This provides a new opportunity for technical exchanges between Russian and Western scientists that can establish an improved and sustained common safety culture for handling these materials. An initiative that develops and uses personal relationships and joint projects among Russian and Western participants involved in fissile nuclear materials safety management contributes to improving nuclear materials nonproliferation and to making a safer world. Technical exchanges and workshops are being used to systematically identify opportunities in the nuclear fissile materials facilities to improve and ensure the safety of workers, the public, and the environment

  7. Main requirements and criteria for State nuclear material control and accounting

    International Nuclear Information System (INIS)

    Ryazanov, B.G.; Goryunov, V.K.; Erastov, V.V.

    1999-01-01

    The paper presents comments and substantiation of the main requirements and criteria for the State nuclear materials (NM) control and accounting system in the draft of the federal Main regulations of NM control and accounting. The State NM control and accounting system structure and design principles, the list of nuclear and special non-nuclear materials which are subject to the control and accounting, NM control and accounting principles are considered. Measurement system for the values for NM control and accounting and measurement assurance program, NM transfer procedures, physical inventory taking, closing a material balance and evaluation of inventory difference and balance closure of bulk form NM are shown. Accounting units in the inventory, the system accounting report documentation and preliminary notifications, the NM control and accounting arrangement, the federal and departmental control in the State NM control and accounting system, the State NM control and accounting system supervision and requirement to the personnel carrying out the NM control and accounting are discussed [ru

  8. Detection of nuclear material by photon activation inside cargo containers

    Science.gov (United States)

    Gmar, Mehdi; Berthoumieux, Eric; Boyer, Sébastien; Carrel, Frédérick; Doré, Diane; Giacri, Marie-Laure; Lainé, Frédéric; Poumarède, Bénédicte; Ridikas, Danas; Van Lauwe, Aymeric

    2006-05-01

    Photons with energies above 6 MeV can be used to detect small amounts of nuclear material inside large cargo containers. The method consists in using an intense beam of high-energy photons (bremsstrahlung radiation) in order to induce reactions of photofission on actinides. The measurement of delayed neutrons and delayed gammas emitted by fission products brings specific information on localization and quantification of the nuclear material. A simultaneous measurement of both of these delayed signals can overcome some important limitations due to matrix effects like heavy shielding and/or the presence of light elements as hydrogen. We have a long experience in the field of nuclear waste package characterization by photon interrogation and we have demonstrated that presently the detection limit can be less than one gram of actinide per ton of package. Recently we tried to extend our knowledge to assess the performance of this method for the detection of special nuclear materials in sea and air freights. This paper presents our first results based on experimental measurements carried out in the SAPHIR facility, which houses a linear electron accelerator with the energy range from 15 MeV to 30 MeV. Our experiments were also modeled using the full scale Monte Carlo techniques. In addition, and in a more general frame, due to the lack of consistent data on photonuclear reactions, we have been working on the development of a new photonuclear activation file (PAF), which includes cross sections for more than 600 isotopes including photofission fragment distributions and delayed neutron tables for actinides. Therefore, this work includes also some experimental results obtained at the ELSA electron accelerator, which is more adapted for precise basic nuclear data measurements.

  9. A open-quotes Newclose quotes regime for nuclear weapons and materials

    International Nuclear Information System (INIS)

    Sutcliffe, W.G.

    1994-01-01

    In this paper, I discuss the principal ideas that I covered in my presentation on December 8, 1993, at the Future of Foreign Nuclear Materials Symposium held by the Naval Postgraduate School in Monterey, California. I was asked to discuss issues related to military inventories of plutonium, and I took this opportunity to describe a possible declaratory regime that could encompass military as well as civilian inventories of plutonium. The open-quote newclose quotes in the title does not imply that the regime discussed here is an original idea. Rather, the regime will be open-quotes new,close quotes when it is adopted. The regime proposed here and in other works is one in which all stocks of nuclear weapons and materials are declared. Originally, declarations were proposed as a traditional arms control measure. Here, declarations are proposed to support the prevention of misuse of nuclear weapons and materials, including support for the nonproliferation regime. In the following, I discuss: (1) Worldwide inventories of nuclear weapons and materials, including the fact that military plutonium must be viewed as part of that worldwide inventory. (2) Life cycles of nuclear weapons and materials, including the various stages from the creation of nuclear materials for weapons through deployment and retirement of weapons to the final disposition of the materials. (3) Mechanisms for making declarations. (4) Risks and benefits to be derived from declarations. (5) Possibilities for supporting evidence or verification

  10. Technologies for detection of nuclear materials

    International Nuclear Information System (INIS)

    DeVolpi, A.

    1996-01-01

    Detection of smuggled nuclear materials at transit points requires monitoring unknown samples in large closed packages. This review contends that high-confidence nuclear-material detection requires induced fission as the primary mechanism, with passive radiation screening in a complementary role. With the right equipment, even small quantities of nuclear materials are detectable with a high probability at transit points. The equipment could also be linked synergistically with detectors of other contrabond. For screening postal mail and packages, passive monitors are probably more cost-effective. When a suspicious item is detected, a single active probe could then be used. Until active systems become mass produced, this two-stage screening/interrogation role for active/passive equipment is more economic for cargo at border crossings. For widespread monitoring of nuclear smuggling, it will probably be necessary to develop a system for simultaneously detecting most categories of contraband, including explosives and illicit drugs. With control of nuclear materials at known storage sites being the first line of defense, detection capabilities at international borders could establish a viable second line of defense against smuggling

  11. Prevention of the inadvertent movement and illicit trafficking of radioactive and nuclear materials in Argentine border

    International Nuclear Information System (INIS)

    Bonet Duran, Stella M.; Canibano, Javier A.; Menossi, Sergio A.; Rodriguez, Carlos E.

    2004-01-01

    The inadvertent and illegal movements of radioactive and nuclear materials are issues of increased national and international awareness. States are progressively becoming more conscious of the need to adequately respond to these events. As regards the States' regulatory infrastructure, the design and enforcement of control and verification measures to maintain the continuity of knowledge about possession, use and movements of radioactive and nuclear materials is of critical importance. The existence of an appropriate legislative framework and a regulatory authority empowered to establish effective safety and security measures are essential to prevent inadvertent and illegal movements of nuclear materials and other radioactive materials. The events of Sep. 11, 2001 in the US have increased the States' awareness on the need to review their national infrastructure to identify additional measures against inadvertent and illegal movements of radioactive and nuclear materials as well as against sabotage of nuclear facilities. Argentina has more than a half- century- old tradition regarding the control and supervision of all activities involving the use of nuclear and radioactive materials. The Nuclear Regulatory Authority (ARN) of Argentina is the organization with federal competence in radiation protection, nuclear safety, safeguards and physical protection. It is responsible for issuing licenses and permits to any activity involving radioactive materials and for controlling and verifying that these activities are performed in full compliance with ARN standards and requirements. In the region, Argentina has been playing an important role in the prevention of illicit traffic of nuclear and radioactive materials for the last years within the framework of Security Commission of MERCOSUR. The last goals of this initiative are to define and coordinate actions and to establish a set of common operational procedures in the countries participating in the mentioned multilateral

  12. Metabonomics for detection of nuclear materials processing.

    Energy Technology Data Exchange (ETDEWEB)

    Alam, Todd Michael; Luxon, Bruce A. (University Texas Medical Branch); Neerathilingam, Muniasamy (University Texas Medical Branch); Ansari, S. (University Texas Medical Branch); Volk, David (University Texas Medical Branch); Sarkar, S. (University Texas Medical Branch); Alam, Mary Kathleen

    2010-08-01

    Tracking nuclear materials production and processing, particularly covert operations, is a key national security concern, given that nuclear materials processing can be a signature of nuclear weapons activities by US adversaries. Covert trafficking can also result in homeland security threats, most notably allowing terrorists to assemble devices such as dirty bombs. Existing methods depend on isotope analysis and do not necessarily detect chronic low-level exposure. In this project, indigenous organisms such as plants, small mammals, and bacteria are utilized as living sensors for the presence of chemicals used in nuclear materials processing. Such 'metabolic fingerprinting' (or 'metabonomics') employs nuclear magnetic resonance (NMR) spectroscopy to assess alterations in organismal metabolism provoked by the environmental presence of nuclear materials processing, for example the tributyl phosphate employed in the processing of spent reactor fuel rods to extract and purify uranium and plutonium for weaponization.

  13. The optimization design of nuclear measurement teaching equipment

    International Nuclear Information System (INIS)

    Tang Rulong; Qiu Xiaoping

    2008-01-01

    So far domestic student-oriented experimental nuclear measuring instruments are used only to measure object density, thickness or material level, and in the choice of sources activity is mostly about 10 mCi. this design will proposed a optimization program dealing with domestic situation. It discussed the radioactive sources activity, the structural design of sealed sources, such as the choice of the tested material in order to get a program optimization. The program used 1 mCi activity radioactive sources 137 Cs to reduce the radiation dose, and the measurement function was improved. So that the apparatus can measure density, thickness nad material level. (authors)

  14. Peculiarities of physical protection assurance of the nuclear materials at nuclear installation decommissioning stage

    International Nuclear Information System (INIS)

    Pinchuk, M.G.

    2001-01-01

    objective is timely prevention, detection of and response to the attempts to use accounted nuclear material for illicit trafficking. In addition to traditional measures, a centralized automated system to detect unauthorized intrusion, to register and suppress the penetration attempts and to organize controlled access to nuclear installation Chernobyl NPP and its internal areas is being established. This system covers three levels of hierarchical physical protection system of all facilities of Chernobyl NPP. The distinguishing features of this system are: high level of stability and reliability, automatic self-diagnostic functions, detection of performance intrusion and restoration of the normal operability. This system has a number of local physical protection subsystems which are the key data base users and are capable to operate off-line in case of the short-time loss of connection with the top level. The access means will include full-height turnstiles and tripods. In the areas of particular importance video identification is envisaged. Passive remote inductive cards encoded on-site will be used as passes. In addition, the issue of control, accountancy and physical protection to be exercised throughout the whole process of fuel discharge, cooling and transportation to KHOYAT -2 (interim storage facility), which will house nuclear material of the total activity more than 1.2 million Ci and about 4.00 tonnes Pu-239, is under review. It is envisaged to create complex to support nuclear material management processes. A provisional engineering solution provides for visual control and video recording, automated record of processes, casks' integrity control, communication means, blocking of the further operations when the precedent operations are inconsistent with QA program requirements, routing control and response forces notification. It shall be emphasized that so far we do not know for sure the amount of nuclear and radioactive materials inside the Shelter Object which is

  15. Material Control and Accountability Measurements for FB-Line Processes

    International Nuclear Information System (INIS)

    Casella, V.R.

    2002-01-01

    This report provides an overview of FB-Line processes and nuclear material accountability measurements. Flow diagrams for the product, waste, and packaging and stabilization processes are given along with the accountability measurements done before and after each of these processes. Brief descriptions of these measurements are provided. This information provides a better understanding of the general FB-Line processes and how MC and A measurements are used to keep track of the accountable material inventory

  16. Role of nuclear material accounting and control on nuclear security. Countermeasure against insider threat

    International Nuclear Information System (INIS)

    Osabe, Takeshi

    2014-01-01

    Possibility on unauthorized removal (theft) of nuclear material by a facility insider is a recognized as a serious threat. An insider could take advantage or knowledge of control system and access to nuclear material to intercept facility's system designed to protect theft of nuclear material by an insider. This paper will address how the facility level Nuclear Material Accounting and Control (NMAC) System should be designed and implemented to enhance deterring and detect theft of nuclear material by a facility insider. (author)

  17. Ukrainian efforts in preventing illicit trafficking in nuclear materials and other radioactive sources

    International Nuclear Information System (INIS)

    Kondratov, S.I.

    1998-01-01

    The Ukrainian efforts in preventing illicit trafficking in nuclear materials and other radioactive sources are described. Attention is paid for Ukrainian Government's Decree intended, in particular, to facilitate in establishing well-coordinated activities of the Ukrainian law enforcement bodies and other agencies involved, assigning the status of the main expert organization on illicit trafficking in nuclear materials to the Scientific Center 'Institute for Nuclear Research', in developing the three-years Program on prevention illicit trafficking in nuclear materials and other radioactive sources on the Ukrainian territory as well as measures at the State and customs borders. The main directions provided by the draft Program mentioned are presented as well. (author)

  18. Problems on shipping high-enriched nuclear materials

    International Nuclear Information System (INIS)

    Ganzha, V.V.; Demko, N.A.; Deryavko, I.I.; Zelenski, D.I.; Kolbaenkov, A.N.; Pivovarov, O.S.; Storozhenko, A.N.; Chernyad'ev, V.V.; Yakovlev, V.V.; Gorin, N.V.; Prokhod'ko, A.I.; Sherbina, A.N.; Barsanov, V.I.; Dyakov, E.K.; Tishenko, M.F.; Khlystov, A.I.; Vasil'ev, A.P.; Smetannikov, V.P.

    1998-01-01

    In 1996-1998 all Russian nuclear materials were taken out of the Institute of Atomic Energy of Kazakhstan National Nuclear Centre (IAE NNC RK). In this report there are basic tasks related to the performance of this work. They are: 1) Preparation of Russian nuclear materials (NM) kept at IAE NNC RK for transportation; 2) accounting and control of Russian nuclear materials kept at IAE NNC RK; 3) arrangement of permit papers for NM transportation; 4) NM transportation from IAE NNC RK to the enterprises of Russian MINATOM; 5) provision of nuclear and radiation safety in the course of operations with NM; 6) provision of physical protection for Russian NM

  19. Implementing of the nuclear materials accounting and control computerized system at JINR

    International Nuclear Information System (INIS)

    Dobryanskij, V.M.; Kalyakin, N.N.; Koltin, G.P.; Samojlov, V.N.; Cheker, A.V.; Shestakov, B.A.

    2000-01-01

    The results of the development of the computerized nuclear materials accounting system at the Joint Institute for Nuclear Research (JINR) are submitted. This work was carried out under Russian-American Nuclear Materials Protection, Control and Accounting (MPCandA) Program. The System was implemented at the Institute, it was attested to work with sensitive information. The computerized information nuclear materials accounting and control system, named MTIS (Materials Tracking Information System), is intended for the automated accounting of the nuclear materials used in JINR, tracking their moving, changes of their inventory amounts, preparation of the required documentation, and also for information support of the measures spent in the JINR on MPCandA program. MTIS can prepare reports for federal level and can also generate data to be reported for internal purposes. MTIS includes as one of the subsystems a program module to prepare reporting information to the Federal Information System (FIS). The system MTIS provides control of access to the database (DB), protection of the information against the non-authorized access, division of the data into the sensitive and non-sensitive data. (author)

  20. Active neutron technique for detecting attempted special nuclear material diversion

    International Nuclear Information System (INIS)

    Smith, G.W.; Rice, L.G. III.

    1979-01-01

    The identification of special nuclear material (SNM) diversion is necessary if SNM inventory control is to be maintained at nuclear facilities. (Special nuclear materials are defined for this purpose as either 235 U of 239 Pu.) Direct SNM identification by the detection of natural decay or fission radiation is inadequate if the SNM is concealed by appropriate shielding. The active neutron interrogation technique described combines direct SNM identification by delayed fission neutron (DFN) detection with implied SNM detection by the identification of materials capable of shielding SNM from direct detection. This technique is being developed for application in an unattended material/equipment portal through which items such as electronic instruments, packages, tool boxes, etc., will pass. The volume of this portal will be 41-cm wide, 53-cm high and 76-cm deep. The objective of this technique is to identify an attempted diversion of at least 20 grams of SNM with a measurement time of 30 seconds

  1. The Physical Protection of Nuclear Material and Nuclear Facilities; Proteccion Fisica De Los Materiales Y Las Instalaciones Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-06-15

    Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international co-operation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and nuclear materials, particularly when such materials are transported across national frontiers [Spanish] La proteccion fisica contra el robo o la desviacion no autorizada de materiales nucleares y contra el sabotaje de las instalaciones nucleares por parte de individuos o grupos es motivo de preocupacion nacional e internacional desde hace mucho tiempo. Aunque la obligacion de crear y hacer funcionar un sistema completo de proteccion fisica de las instalaciones y materiales nucleares en el territorio de un Estado determinado incumbe exclusivamente al Gobierno de dicho Estado, el que esa obligacion se cumpla o no, y si se cumple, en que medida o hasta que punto, son cosas que no dejan indiferentes a los demas Estados. Por ello, la proteccion fisica se ha convertido en motivo de interes y cooperacion internacional. La necesidad de la cooperacion internacional se hace evidente en los casos en que la eficacia de la proteccion fisica en el territorio de un Estado depende de que otros Estados tomen tambien medidas apropiadas para evitar o hacer fracasar los actos hostiles dirigidos contra instalaciones y

  2. Study of nuclear environment and material strategy

    International Nuclear Information System (INIS)

    Kamei, Takashi

    2011-01-01

    There is a concern about the environmental hazard caused by radioactive materials coming with the expansion of nuclear power and even by renewable energies, which are used as countermeasures against global warming to construct a sustainable society. A concept to internalize the pollution caused by radioactive materials, which are directly or indirectly related to nuclear power, to economical activities by adopting externality is proposed. Energy and industrial productions are strongly related to the supply of material. Therefore material flow is also part of this internalization concept. The concept is named 'NEMS (Nuclear Environment and Material Strategy)'. Fission products and transuranic isotopes from nuclear power such as plutonium are considered in this concept. Thorium, which comes from the material flow of rare-earth production to support the elaboration of renewable energies including electric vehicles on the consumer side, is considered as an externality of the non-nuclear power field. Fission products contain some rare-earth materials. Thus, these rare-earth materials, which are extracted by the advanced ORIENT (Optimization by Recycling Instructive Elements) cycle, are internalized as rare-earth supplier in economy. However, the supply quantity is limited. Therefore rare-earth production itself is still needed. The externality of rare-earth production is thorium and is internalized by using it as nuclear fuel. In this case, the demand of thorium is still small within these few decades compared to the production of thorium as byproduct of the rare-earth production. A thorium energy bank (The Bank) is advanced to regulate the storage of the excess amount of thorium inside of an international framework in order to prevent environmental hazard resulting from the illegal disposal of thorium. In this paper, the material flows of thorium and rare-earth are outlined. Their material balance are demonstrated based on the prediction of rare-earth mining and an

  3. Decree No. 208 On National Accounting and Control System of the Nuclear Materials

    International Nuclear Information System (INIS)

    1996-01-01

    The present Decree establishes the arrangements to formalize the National Accounting and Control System of the Nuclear Materials, the which one has the objectives of contributing to an efficient and economic management of the nuclear materials in the national territory; to establish the arrangements directed to detect any employment, lost or unauthorized movement of the nuclear material; and to establish the measures of necessary control to give fulfillment to the international commitments assumed by the Cuban State in relationship to the nuclear materials, important components, or both. It also establishes the following responsibilities: The Ministry of Science Technology and Environment is the Organism of the Central Administration of the State responsible for the supervision and control of the dispositions and it delegates in the National Center of Nuclear Security the execution of the functions assigned to this Ministry

  4. A shielded measurement system for irradiated nuclear fuel measurements

    International Nuclear Information System (INIS)

    Mosby, W.R.; Aumeier, S.E.; Klann, R.T.

    1999-01-01

    The US Department of Energy (DOE) is driving a transition toward dry storage of irradiated nuclear fuel (INF), toward characterization of INF for final disposition, and toward resumption of measurement-based material control and accountability (MC and A) efforts for INF. For these reasons, the ability to efficiently acquire radiological measurements of INF in a dry environment is important. The DOE has recently developed a guidance document proposing MC and A requirements for INF. The intent of this document is to encourage the direct measurement of INF on inventory within DOE. The guidance document reinforces and clarifies existing material safeguards requirements as they pertain to INF. Validation of nuclear material contents of non-self-protecting INF must be accomplished by direct measurement, application of validated burnup codes using qualified initial fissile content, burnup data, and age or by other valid means. The fuel units must remain intact with readable identification numbers. INF may be subject to periodic inventories with visual item accountability checks. Quantitative measurements may provide greater assurance of the integrity of INF inventories at a lower cost and with less personnel exposure than visual item accountability checks. Currently, several different approaches are used to measure the radiological attributes of INF. Although these systems are useful for a wide variety of applications, there is currently no relatively inexpensive measurement system that is readily deployable for INF measurements for materials located in dry storage. The authors present the conceptual design of a shielded measurement system (SMS) that could be used for this purpose. The SMS consists of a shielded enclosure designed to house a collection of measurement systems to allow measurements on spent fuel outside of a hot cell. The phase 1 SMS will contain 3 He detectors and ionization chambers to allow for gross neutron and gamma-ray measurements. The phase 2 SMS

  5. Nuclear materials management handbook. Safeguards, physical protection of nuclear material. 1995 ed.

    International Nuclear Information System (INIS)

    1995-01-01

    Now, very safe and stable supply of electric power has become to be obtained by nuclear energy, and Japan has steadily promoted nuclear power as the basic energy that contributes to overcome the unstable structure of energy supply in Japan highly depending on foreign countries, as shown in the long term plan of the research, development and utilization of nuclear power. Great progress was observed in nuclear fuel recycling in Japan such as the attainment of initial criticality of the prototype FBR 'Monju' and the start of construction of the commercial fuel reprocessing plant in Rokkasho. Recently the recognition of the importance of nuclear substance management has heightened, and the measures for maintaining and strengthening the reliability of nuclear nonproliferation system are investigated. It is important that Japan strictly observes the nuclear nonproliferation system based on the NPT which was extended infinitely. In this handbook, the outline of the measures for nuclear nonproliferation and safeguard and the protection of nuclear substances, the treaties and agreements and the national laws related to these are described. (K.I.)

  6. Nuclear materials 1993 annual report. Volume 8, No. 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-05-01

    This annual report of the US Nuclear Regulatory Commission`s Office for Analysis and Evaluation of Operational Data (AEOD) describes activities conducted during 1993. The report is published in two parts. NUREG-1272, Vol. 8, No. 1, covers power reactors and presents an overview of the operating experience of the nuclear power industry from the NRC perspective, including comments about the trends of some key performance measures. The report also includes the principal findings and issues identified in AEOD studies over the past year and summarizes information from such sources as licensee event reports, diagnostic evaluations, and reports to the NRC`s Operations Center. NUREG-1272, Vol. 8, No. 2, covers nuclear materials and presents a review of the events and concerns during 1993 associated with the use of licensed material in nonreactor applications, such as personnel overexposures and medical misadministrations. Note that the subtitle of No. 2 has been changed from ``Nonreactors`` to ``Nuclear Materials.`` Both reports also contain a discussion of the Incident Investigation Team program and summarize both the Incident Investigation Team and Augmented Inspection Team reports. Each volume contains a list of the AEOD reports issued from 1980 through 1993.

  7. Nuclear materials 1993 annual report. Volume 8, No. 2

    International Nuclear Information System (INIS)

    1995-05-01

    This annual report of the US Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data (AEOD) describes activities conducted during 1993. The report is published in two parts. NUREG-1272, Vol. 8, No. 1, covers power reactors and presents an overview of the operating experience of the nuclear power industry from the NRC perspective, including comments about the trends of some key performance measures. The report also includes the principal findings and issues identified in AEOD studies over the past year and summarizes information from such sources as licensee event reports, diagnostic evaluations, and reports to the NRC's Operations Center. NUREG-1272, Vol. 8, No. 2, covers nuclear materials and presents a review of the events and concerns during 1993 associated with the use of licensed material in nonreactor applications, such as personnel overexposures and medical misadministrations. Note that the subtitle of No. 2 has been changed from ''Nonreactors'' to ''Nuclear Materials.'' Both reports also contain a discussion of the Incident Investigation Team program and summarize both the Incident Investigation Team and Augmented Inspection Team reports. Each volume contains a list of the AEOD reports issued from 1980 through 1993

  8. Heat resistant materials and their feasibility issues for a space nuclear transportation system

    International Nuclear Information System (INIS)

    Olsen, C.S.

    1991-01-01

    A number of nuclear propulsion concepts based on solid-core nuclear propulsion are being evaluated for a nuclear propulsion transportation system to support the Space Exploration Initiative (SEI) involving the reestablishment of a manned lunar base and the subsequent exploration of Mars. These systems will require high-temperature materials to meet the operating conditions with appropriate reliability and safety built into these systems through the selection and testing of appropriate materials. The application of materials for nuclear thermal propulsion (NTP) and nuclear electric propulsion (NEP) systems and the feasibility issues identified for their use will be discussed. Some mechanical property measurements have been obtained, and compatibility tests were conducted to help identify feasibility issues. 3 refs., 1 fig., 4 tabs

  9. Concepts of IAEA nuclear materials accounting

    International Nuclear Information System (INIS)

    Oakberg, John A.

    2001-01-01

    The paper describes nuclear material accounting from the standpoint of IAEA Safeguards and how this accounting is applied by the Agency. The basic concepts of nuclear material accounting are defined and the way these apply to States with INFCIRC/153-type safeguards agreements is presented. (author)

  10. Nuclear medicine environmental discharge measurement. Final report

    International Nuclear Information System (INIS)

    Gesell, T.F.; Prichard, H.M.; Davis, E.M.; Pirtle, O.L.; DiPietro, W.

    1975-06-01

    The discharge of most man-made radioactive materials to the environment is controlled by Federal, State or local regulatory agencies. Exceptions to this control include the radioactive wastes eliminated by individuals who have undergone diagnostic or therapeutic nuclear medicine procedures. The purpose of this study is to estimate the amount of radioactivity released to the environment via the nuclear medicine pathway for a single sewage drainage basin and to measure the amounts discharged to the environment. The report is organized into a review of previous studies, scope of work, facility data, environmental measurements and estimates of population exposure

  11. Improvement of technical measures to detect and respond to illicit trafficking of nuclear and radioactive materials [Results of a coordinated research project 2003-2006

    International Nuclear Information System (INIS)

    2008-07-01

    This publication summarizes the research conducted during an IAEA Coordinated Research Project (CRP) undertaken to address technical and operational difficulties in the detection of and response to illicit trafficking of nuclear material. Equipment to detect illicit trafficking of nuclear and radioactive materials at borders has specific technical and operational requirements that are very different from equipment used in other radiation monitoring cases. Automated and manual measurements need to be done in the field, often outdoors, at land or sea borders, crossing points or airports. The free flow of goods and passengers must not be impacted, thus requiring that the measurement time be short. The design needs to take into account that the users of the equipment are not experts in radiation detection; thus the results of the measurements should be easy to understand

  12. Nuclear Security Recommendations on Physical Protection of Nuclear Material and Nuclear Facilities (INFCIRC/225/Revision 5): Recommendations

    International Nuclear Information System (INIS)

    2011-01-01

    This publication, Revision 5 of Physical Protection of Nuclear Material and Nuclear Facilities (INFCIRC/225), is intended to provide guidance to States and their competent authorities on how to develop or enhance, implement and maintain a physical protection regime for nuclear material and nuclear facilities, through the establishment or improvement of their capabilities to implement legislative and regulatory programmes. The recommendations presented in this publication reflect a broad consensus among IAEA Member States on the requirements which should be met for the physical protection of nuclear materials and nuclear facilities.

  13. IBA studies of helium mobility in nuclear materials revisited

    Energy Technology Data Exchange (ETDEWEB)

    Trocellier, P., E-mail: patrick.trocellier@cea.fr [CEA, DEN, Service de Recherches de Métallurgie Physique, Laboratoire JANNUS, F-91191 Gif-sur-Yvette (France); Agarwal, S.; Miro, S. [CEA, DEN, Service de Recherches de Métallurgie Physique, Laboratoire JANNUS, F-91191 Gif-sur-Yvette (France); Vaubaillon, S. [CEA, DEN, Service de Recherches de Métallurgie Physique, Laboratoire JANNUS, F-91191 Gif-sur-Yvette (France); CEA, INSTN, UEPTN, F-91191 Gif-sur-Yvette (France); Leprêtre, F.; Serruys, Y. [CEA, DEN, Service de Recherches de Métallurgie Physique, Laboratoire JANNUS, F-91191 Gif-sur-Yvette (France)

    2015-12-15

    The aim of this paper is to point out and to discuss some features extracted from the study of helium migration in nuclear materials performed during the last fifteen years using ion beam analysis (IBA) measurements. The first part of this paper is devoted to a brief description of the two main IBA methods used, i.e. deuteron induced nuclear reaction for {sup 3}He depth profiling and high-energy heavy-ion induced elastic recoil detection analysis for {sup 4}He measurement. In the second part, we provide an overview of the different studies carried out on model nuclear waste matrices and model nuclear reactor structure materials in order to illustrate and discuss specific results in terms of key influence parameters in relation with thermal or radiation activated migration of helium. Finally, we show that among the key parameters we have investigated as able to influence the height of the helium migration barrier, the following can be considered as pertinent: the experimental conditions used to introduce helium (implanted ion energy and implantation fluence), the grain size of the matrix, the lattice cell volume, the Young's modulus, the ionicity degree of the chemical bond between the transition metal atom M and the non-metal atom X, and the width of the band gap.

  14. Nuclear materials management for safety and efficiency

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1965-12-15

    The use of nuclear materials in industrial processes presents management with some special problems which are peculiar to the atomic energy industry. If reactor fuel costs are to be kept low, too, each fuel element must yield the maximum economic 'bum-up' before it is withdrawn from service, and this calls for reliable non-destructive methods of measurement of 'burn-up' and appropriate records and fuel-changing schedules. The special hazards of radioactive materials call for special precautions and appropriate systems of handling and storage. A further danger unique to atomic energy is that of criticality - the possibility that an excessive concentration of fissile material may result in a chain reaction. Every part of the processing plant must be surveyed and checked to ensure that there is no build-up of fissile residues; in storage or transit there must be no aggregation of small lots. In the nuclear energy industry, too, the standards of purity required are much higher than in most other large-scale operation, so that stringent quality checks are needed

  15. Nuclear Materials Management for the Nevada Test Site (NTS)

    International Nuclear Information System (INIS)

    Jesse C. Schreiber

    2007-01-01

    The Nevada Test Site (NTS) has transitioned from its historical role of weapons testing to a broader role that is focused on being a solution to multiple National Nuclear Security Administration (NNSA) challenges and opportunities with nuclear materials for the nation. NTS is supporting other NNSA sites challenged with safe nuclear materials storage and disposition. NNSA, with site involvement, is currently transforming the nuclear stockpile and supporting infrastructure to meet the 2030 vision. Efforts are under way to make the production complex smaller, more consolidated, and more modern. With respect to the nuclear material stockpile, the NNSA sites are currently reducing the complex nuclear material inventory through dispositioning and consolidating nuclear material. This includes moving material from other sites to NTS. State-of-the-art nuclear material management and control practices at NTS are essential for NTS to ensure that these new activities are accomplished in a safe, secure, efficient, and environmentally responsible manner. NTS is aggressively addressing this challenge

  16. Annual progress report on nuclear data 1983 of the Central Bureau for Nuclear Measurements, Geel (Belgium)

    International Nuclear Information System (INIS)

    1984-05-01

    In this progress report of the Central Bureau for Nuclear Measurements at Geel (Belgium) researches related to neutron data and to non-neutron nuclear data are gathered. Neutron data are essentially related to cross-section measurements: for instance, concerning actinides, structural materials as Cr and Fe, fission products. Some studies are classified as concerning standard neutron data. Underlying physics is no forgotten neither than equipment (linear accelerator). Non-neutron nuclear data is concerned essentially with decay studies. Some compilations and evaluations are also given. Improvement of measurement and source preparation techniques is a part of this section

  17. Radiation Detection System for Prevention of Illicit Trafficking of Nuclear and Radioactive Materials

    International Nuclear Information System (INIS)

    Kwak, Sung Woo; Chang, Sung Soon; Yoo, Ho Sik

    2010-01-01

    Fixed radiation portal monitors (RPMs) deployed at border, seaport, airport and key traffic checkpoints have played an important role in preventing the illicit trafficking and transport of nuclear and radioactive materials. However, the RPM is usually large and heavy and can't easily be moved to different locations. These reasons motivate us to develop a mobile radiation detection system. The objective of this paper is to report our experience on developing the mobile radiation detection system for search and detection of nuclear and radioactive materials during road transport. Field tests to characterize the developed detection system were performed at various speeds and distances between the radioactive isotope (RI) transporting car and the measurement car. Results of measurements and detection limits of our system are described in this paper. The mobile radiation detection system developed should contribute to defending public's health and safety and the environment against nuclear and radiological terrorism by detecting nuclear or radioactive material hidden illegally in a vehicle

  18. U.S. national nuclear material control and accounting system

    International Nuclear Information System (INIS)

    Taylor, S; Terentiev, V G

    1998-01-01

    Issues related to nuclear material control and accounting and illegal dealing in these materials were discussed at the April 19--20, 1996 Moscow summit meeting (G7 + Russia). The declaration from this meeting reaffirmed that governments are responsible for the safety of all nuclear materials in their possession and for the effectiveness of the national control and accounting system for these materials. The Russian delegation at this meeting stated that ''the creation of a nuclear materials accounting, control, and physical protection system has become a government priority''. Therefore, in order to create a government nuclear material control and accounting system for the Russian Federation, it is critical to study the structure, operating principles, and regulations supporting the control and accounting of nuclear materials in the national systems of nuclear powers. In particular, Russian specialists have a definite interest in learning about the National Nuclear Material Control and Accounting System of the US, which has been operating successfully as an automated system since 1968

  19. Management review of nuclear material control and accounting systems

    International Nuclear Information System (INIS)

    1975-06-01

    Section 70.58, ''Fundamental Nuclear Material Controls,'' of 10 CFR Part 70, ''Special Nuclear Materials,'' requires, in paragraph 70.58(c), that certain licensees authorized to possess more than one effective kilogram of special nuclear material establish a management system to provide for the development, revision, implementation, and enforcement of nuclear material control and accounting procedures. Such a system must provide for a review of the nuclear material control system at least every 12 months. This guide describes the purpose and scope, personnel qualifications, depth of detail, and procedures that are acceptable to the NRC staff for the management review of nuclear material control systems required under paragraph 70.58(c) of 10 CFR Part 70. (U.S.)

  20. Base isolation for nuclear power and nuclear material facilities

    International Nuclear Information System (INIS)

    Eidinger, J.M.; Kircher, C.A.; Vaidya, N.; Constantinou, M.; Kelly, J.M.; Seidensticker, R.; Tajirian, F.F.; Ovadia, D.

    1989-01-01

    This report serves to document the status of the practice for the use of base isolation systems in the design and construction of nuclear power and nuclear material facilities. The report first describes past and current (1989) applications of base isolation in nuclear facilities. The report then provides a brief discussion of non-nuclear applications. Finally, the report summarizes the status of known base-isolation codes and standards

  1. Technology development for nuclear material accountability

    International Nuclear Information System (INIS)

    Hong, Jong Sook; Lee, Byung Doo; Cha, Hong Ryul; Choi, Hyoung Nae; Park, Ho Jun.

    1990-01-01

    Neutron yields from 19 F(α,n) 22 Na reaction of uranium neutron interaction with uranium-bass materials, and the characteristics of shielded neutron assay probe have been studied. On the basis of the above examination, U-235 enrichment in UF 6 cylinders like model 30B and model 48Y was measured by the reaction and U-235 contents in the containers by non-destructive total passive neutron assay method. Total measurement efficiency as a result was found to be 6.44 x 10 -4 and 1.25 x 10 -4 for model 30B and model 40Y UF 6 cylinder, respectively. The uncertainty of measured enrichment as compared to Tag value obtained from chemical analysis approached about 5 % of relative error at 95 % confidence interval. In the follow-up action for the previously developed (1988) computer system of nuclear material accounting the error searching and treatment routine in accordance with code 10, of IAEA and respective facility attachment has been added to easing the burden of manual error correction by operator. In addition, the procedure for LEMUF calculation has been prepared to help bulk facility operators evaluating MUF in the period of material balance. (author)

  2. Dealing with the regional challenge of physical protection of nuclear materials

    International Nuclear Information System (INIS)

    Paschoa, A.S.

    2002-01-01

    Full text: The problem of protecting sensitive fissile and fissionable nuclear materials of misuses by governments has been the subject of the convention on physical protection of nuclear material (CPPNM), which entered into force on February 8, 1987. However, in May 2001 the final report of the expert meeting had already recognized 'a clear need to strengthen the international physical protection regime'. The board of governors of the International Atomic Energy Agency (IAEA) decided then to convene a group, which would meet in Vienna from 3 to 7 December 2001, to draft on amendment to the CPPNM. The tragic occurrences of September 11, 2001, however, changed the then generally accepted view on the problem of physical protection, because nuclear materials had to be protected from falling into the hands of terrorists rather than of governments thirst of nuclear sensitive materials. Moreover, crude explosive devices could be made by terrorists, or hired scientists, using readily available radioactive materials, like 226 Ra or 137 Cs to inflict damage to civilians. Thus physical protection of those and other radioactive materials became an instant challenge for national and international authorities to prevent the use of such materials in terrorist actions. The prevention of illicit trafficking of radioactive materials is now in the priority list of these authorities. Fortunately; an international conference on 'Measures to Detect, Intercept and Respond to the Illicit Uses of Nuclear Materials and Radioactive Sources' was held in Stockholm, Sweden, in May 2001. An IAEA document - GOV/2001/37-GC(45)/20 - recommended in its plan of activities a series of projects to be implemented between 2002 and 2005, which included developing and providing assistance for the application of: (i) standards for physical protection of nuclear materials and nuclear facilities in member states; (ii) norms and guidelines for nuclear material accounting and control in member states; (iii

  3. Order for execution of the law concerning regulation of nuclear source materials, nuclear fuel materials and reactors

    International Nuclear Information System (INIS)

    1977-01-01

    The designations according to Item 1, Article 3 and Item 1, Article 13 of the Law must be obtained for each factory or business place where refining and fabrication of nuclear material are to be performed. One who wants to obtain such designation should file an application attached with a business plan and other documents via the director of a regional bureau of international trade and industry having jurisdiction over such factory or business place. When nuclear material refiners and nuclear material fabricators wish to obtain the approval for change stipulated in Item 1, Article 6 and Item 1, Article 16 of the Law, they must file applications to the Prime Minister and the Minister of International Trade and Industry via said directors. Chief handlers of nuclear fuel materials shall be approved among those meeting the strict requirements. One who wishes to install reactors must obtain the approval for each factory or business place where the reactors are to be installed. The permission must be obtained for each nuclear ship entering Japanese waters. The reactors proper and several facilities are subject to periodic inspection. (Rikitake, Y.)

  4. Nuclear material safeguards surveillance and accountancy by isotope correlation techniques

    International Nuclear Information System (INIS)

    Persiani, P.J.; Goleb, J.A.; Kroc, T.K.

    1981-11-01

    The purpose of this study is to investigate the applicability of isotope correlation techniques (ICT) to the Light Water Reactor (LWR) and the Liquid Metal Fast Breeder Reactor (LMFBR) fuel cycles for nuclear material accountancy and safeguards surveillance. The isotopic measurement of the inventory input to the reprocessing phase of the fuel cycle is the primary direct determination that an anomaly may exist in the fuel management of nuclear material. The nuclear materials accountancy gap which exists between the fabrication plant output and the input to the reprocessing plant can be minimized by using ICT at the dissolver stage of the reprocessing plant. The ICT allows a level of verification of the fabricator's fuel content specifications, the irradiation history, the fuel and blanket assemblies management and scheduling within the reactor, and the subsequent spent fuel assembly flows to the reprocessing plant. The investigation indicates that there exist relationships between isotopic concentration which have predictable, functional behavior over a range of burnup. Several cross-correlations serve to establish the initial core assembly-averaged composition. The selection of the more effective functionals will depend not only on the level of reliability of ICT for verification, but also on the capability, accuracy and difficulty of developing measurement methods. The propagation of measurement errors on the correlation functions and respective sensitivities to isotopic compositional changes have been examined and found to be consistent with current measurement methods

  5. Nuclear reaction analysis of hydrogen in materials: Principals and applications

    International Nuclear Information System (INIS)

    Lanford, W.A.

    1991-01-01

    Analysis for hydrogen in materials is difficult by most traditional analytic methods. Because hydrogen has no Auger transitions, no X-ray transitions, does not neutron activate, and does not backscatter ions, it is invisible in analytical methods based on these effects. In addition, since hydrogen is a universal contaminant in vacuum systems, techniques based on mass spectrometry are difficult unless extreme measures are taken to reduce hydrogen backgrounds. Because of this situation, methods have been developed for analyzing for hydrogen in solid materials based on nuclear reactions between bombarding ions and hydrogen atoms (protons) in the samples. The nuclear reaction methods are now practiced at laboratories around the world. The basic principals of nuclear reaction analysis will be briefly presented. This method will be illustrated by applications to problems ranging from basic physics, to geology, to materials science, and to art history and archeology

  6. Holdup measurement for nuclear fuel manufacturing plants

    International Nuclear Information System (INIS)

    Zucker, M.S.; Degen, M.; Cohen, I.; Gody, A.; Summers, R.; Bisset, P.; Shaub, E.; Holody, D.

    The assay of nuclear material holdup in fuel manufacturing plants is a laborious but often necessary part of completing the material balance. A range of instruments, standards, and a methodology for assaying holdup has been developed. The objectives of holdup measurement are ascertaining the amount, distribution, and how firmly fixed the SNM is. The purposes are reconciliation of material unbalance during or after a manufacturing campaign or plant decommissioning, to decide security requirements, or whether further recovery efforts are justified

  7. Advanced physical protection systems for nuclear materials

    International Nuclear Information System (INIS)

    Jones, O.E.

    1976-01-01

    Because of the increasing incidence of terrorism, there is growing concern that nuclear materials and facilities need improved physical protection against theft, diversion, or sabotage. Physical protection systems for facilities or transportation which have balanced effectiveness include information systems, access denial systems, adequate and timely response, recovery capability, and use denial methods for despoiling special nuclear materials (SNM). The role of these elements in reducing societal risk is described; however, it is noted that, similar to nuclear war, the absolute risks of nuclear theft and sabotage are basically unquantifiable. Sandia Laboratories has a major US Energy Research and Development Administration (ERDA) role in developing advanced physical protection systems for improving the security of both SNM and facilities. These activities are surveyed in this paper. A computer simulation model is being developed to assess the cost-effectiveness of alternative physical protection systems under various levels of threat. Improved physical protection equipment such as perimeter and interior alarms, secure portals, and fixed and remotely activated barriers is being developed and tested. In addition, complete prototype protection systems are being developed for representative nuclear facilities. An example is shown for a plutonium storage vault. The ERDA safe-secure transportation system for highway shipments of all significant quantities of government-owned SNM is described. Adversary simulation as a tool for testing and evaluating physical protection systems is discussed. Finally, a list of measures is given for assessing overall physical protection system performance. (author)

  8. Advanced physical protection systems for nuclear materials

    International Nuclear Information System (INIS)

    Jones, O.E.

    1975-10-01

    Because of the increasing incidence of terrorism, there is growing concern that nuclear materials and facilities need improved physical protection against theft, diversion, or sabotage. Physical protection systems for facilities or transportation which have balanced effectiveness include information systems, access denial systems, adequate and timely response, recovery capability, and use denial methods for despoiling special nuclear materials (SNM). The role of these elements in reducing societal risk is described; however, it is noted that, similar to nuclear war, the absolute risks of nuclear theft and sabotage are basically unquantifiable. Sandia Laboratories has a major Energy Research and Development Administration (ERDA) role in developing advanced physical protection systems for improving the security of both SNM and facilities. These activities are surveyed. A computer simulation model is being developed to assess the cost-effectiveness of alternative physical protection systems under various levels of threat. Improved physical protection equipment such as perimeter and interior alarms, secure portals, and fixed and remotely-activated barriers is being developed and tested. In addition, complete prototype protection systems are being developed for representative nuclear facilities. An example is shown for a plutonium storage vault. The ERDA safe-secure transportation system for highway shipments of all significant quantities of government-owned SNM is described. Adversary simulation as a tool for testing and evaluating physical protection systems is discussed. A list of measures is given for assessing overall physical protection system performance. (auth)

  9. Nuclear physics methods in materials research

    International Nuclear Information System (INIS)

    Bethge, K.; Baumann, H.; Jex, H.; Rauch, F.

    1980-01-01

    Proceedings of the seventh divisional conference of the Nuclear Physics Division held at Darmstadt, Germany, from 23rd through 26th of September, 1980. The scope of this conference was defined as follows: i) to inform solid state physicists and materials scientists about the application of nuclear physics methods; ii) to show to nuclear physicists open questions and problems in solid state physics and materials science to which their methods can be applied. According to the intentions of the conference, the various nuclear physics methods utilized in solid state physics and materials science and especially new developments were reviewed by invited speakers. Detailed aspects of the methods and typical examples extending over a wide range of applications were presented as contributions in poster sessions. The Proceedings contain all the invited papers and about 90% of the contributed papers. (orig./RW)

  10. Gamma spectrometric discrimination of special nuclear materials

    International Nuclear Information System (INIS)

    Dowdall, M.; Mattila, A.; Ramebaeck, H.; Aage, H.K.; Palsson, S.E.

    2012-12-01

    This report presents details pertaining to an exercise conducted as part of the NKS-B programme using synthetic gamma ray spectra to simulate the type of data that may be encountered in the interception of material potentially containing special nuclear materials. A range of scenarios were developed involving sources that may or may not contain special nuclear materials. Gamma spectral data was provided to participants as well as ancillary data and participants were asked, under time constraint, to determine whether or not the data was indicative of circumstances involving special nuclear materials. The situations varied such that different approaches were required in order to obtain the correct result in each context. In the majority of cases participants were able to correctly ascertain whether or not the situations involved special nuclear material. Although fulfilling the primary goal of the exercise, some participants were not in a position to correctly identify with certainty the material involved, Situations in which the smuggled material was being masked by another source proved to be the most challenging for participants. (Author)

  11. Gamma spectrometric discrimination of special nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Dowdall, M. [Norwegian Radiation Protection Authority (Norway); Mattila, A. [Radiation and Nuclear Safety Authority, Helsinki (Finland); Ramebaeck, H. [Swedish Defence Research Agency, Stockholm (Sweden); Aage, H.K. [Danish Emergency Management Agency, Birkeroed (Denmark); Palsson, S.E. [Icelandic Radiation Safety Authority, Reykjavik (Iceland)

    2012-12-15

    This report presents details pertaining to an exercise conducted as part of the NKS-B programme using synthetic gamma ray spectra to simulate the type of data that may be encountered in the interception of material potentially containing special nuclear materials. A range of scenarios were developed involving sources that may or may not contain special nuclear materials. Gamma spectral data was provided to participants as well as ancillary data and participants were asked, under time constraint, to determine whether or not the data was indicative of circumstances involving special nuclear materials. The situations varied such that different approaches were required in order to obtain the correct result in each context. In the majority of cases participants were able to correctly ascertain whether or not the situations involved special nuclear material. Although fulfilling the primary goal of the exercise, some participants were not in a position to correctly identify with certainty the material involved, Situations in which the smuggled material was being masked by another source proved to be the most challenging for participants. (Author)

  12. Materials for nuclear reactors

    International Nuclear Information System (INIS)

    Banerjee, S.; Kamath, H.S.

    2005-01-01

    The improved performance of present generation nuclear reactors and the realization of advanced reactor concepts, both, require development of better materials. Physical metallurgy/materials science principles which have been exploited in meeting the exacting requirements of nuclear reactor materials (fuels and structural materials), are outlined citing a few specific examples. While the incentive for improvement of traditional fuels (e.g., UO 2 fuel) is primarily for increasing the average core burn up, the development of advanced fuels (e.g., MOX, mixed carbide, nitride, silicide and dispersion fuels) are directed towards better utilization of fissile and fertile inventories through adaptation of innovative fuel cycles. As the burn up of UO 2 fuel reaches higher levels, a more detailed and quantitative understanding of the phenomena such as fission gas release, fuel restructuring induced by radiation and thermal gradients and pellet-clad interaction is being achieved. Development of zirconium based alloys for both cladding and pressure tube applications is discussed with reference to their physical metallurgy, fabrication techniques and in-reactor degradation mechanisms. The issue of radiation embrittlement of reactor pressure vessels (RPVs) is covered drawing a comparison between the western and eastern specifications of RPV steels. The search for new materials which can stand higher rates of atomic displacement due to radiation has led to the development of swelling resistant austenitic and ferritic stainless steels for fast reactor applications as exemplified by the development of the D-9 steel for Indian fast breeder reactor. The presentation will conclude by listing various materials related phenomena, which have a strong bearing on the successful development of future nuclear energy systems. (author)

  13. The law for the regulations of nuclear source materials, nuclear fuel materials and reactors

    International Nuclear Information System (INIS)

    1979-01-01

    The law aims to perform regulations on enterprises of refining, processing and reprocessing of nuclear source and fuel materials and on establishment and operation of reactors to realize the peaceful and deliberate utilization of atomic energy according to the principle of the atomic energy basic law. Regulations of use of internationally regulated substances are also envisaged to observe international agreements. Basic concepts and terms are defined, such as: atomic energy; nuclear fuel material; nuclear source material; reactor; refining; processing; reprocessing and internationally regulated substance. Any person besides the Power Reactor and Nuclear Fuel Material Developing Corporation who undertakes refining shall be designated by the Prime Minister and the Minister of International Trade and Industry. An application shall be filed to the ministers concerned, listing name and address of the person, name and location of the refining works, equipment and method of refining, etc. The permission of the Prime Minister is necessary for any person who engages in processing. An application shall be filed to the Prime Minister, listing name and address of the person, name and location of the processing works and equipment and method of processing, etc. Permission of the Prime Minister, the Minister of International Trade and Industry or the Minister of Transport is necessary for any person who sets up reactors. An application shall be filed to the minister concerned, listing name and address of the person, purpose of operation, style, thermal output of reactor and number of units, etc. (Okada, K.)

  14. Measures against illicit trafficking of nuclear materials and other radioactive sources in Nigeria

    International Nuclear Information System (INIS)

    Coker, A.J.; Adesanmi, C.A.

    2001-01-01

    Full text: Introduction: Background Information - The concern worldwide over the dangers associated with illicit trafficking of nuclear materials and other radioactive sources is shared by the Federal Government and people of Nigeria. In order to protect its territories, the government in the second quarter of 1998 gave a directive that Nigeria should be registered as a participating nation in the Illicit Trafficking Database Programme being organised by the International Atomic Energy Agency (IAEA). Immediately, a National Committee (NC) was established comprising all relevant ministries and government agencies, particularly the ones involved in the control and use of radioactive materials, such as the Federal Radiation Protection Service (FRPS), Nuclear Research Centres, Federal Environmental Protection Agency (FEPA), Energy Commission of Nigeria, the Nigerian Police Force, the Customs and the Ports Authority. By August 1998, the committee got Nigeria duly registered with the IAEA as a participating nation and presented a proposal to the Federal Government on how to monitor our ports of entry, borders and the entire country in order to participate effectively in the programme. In other to check illicit trafficking of nuclear materials effectively and efficiently within and across the Nigerian borders, the National Committee gave priority to proper organisational structure, manpower training and development, and the provision of adequate and necessary facilities and infrastructure for nationwide radiation monitoring programme. Organisational Structure - In Nigeria, there is the Nuclear Safety and Radiation Protection Decree No. 19 of 1995 which established the Nuclear Regulatory Authority (NRA) and an Institute of Radiation Protection (IRP). The decree empowers the NRA to regulate the production, possession, transfer, import, export, trade, use, transportation, storage and disposal of radioactive materials and radiation equipment in order to ensure radiation

  15. Automated processing of nuclear materials accounting data

    International Nuclear Information System (INIS)

    Straka, J.; Pacak, P.; Moravec, J.

    1980-01-01

    An automated system was developed of nuclear materials accounting in Czechoslovakia. The system allows automating data processing including data storage. It comprises keeping records of inventories and material balance. In designing the system, the aim of the IAEA was taken into consideration, ie., building a unified information system interconnected with state-run systems of accounting and checking nuclear materials in the signatory countries of the non-proliferation treaty. The nuclear materials accounting programs were written in PL-1 and were tested at an EC 1040 computer at UJV Rez where also the routine data processing takes place. (B.S.)

  16. Passive sensor systems for nuclear material monitoring

    International Nuclear Information System (INIS)

    Simpson, M.L.; Boatner, L.A.; Holcomb, D.E.; McElhaney, S.A.; Mihalczo, J.T.; Muhs, J.D.; Roberts, M.R.; Hill, N.W.

    1993-01-01

    Passive fiber optic sensor systems capable of confirming the presence of special nuclear materials in storage or process facilities are being developed at Oak Ridge National Laboratory (ORNL). These sensors provide completely passive, remote measurement capability. No power supplies, amplifiers, or other active components that could degrade system reliability are required at the sensor location. ORNL, through its research programs in scintillator materials, has developed a variety of materials for use in alpha-, beta-, gamma-, and neutron-sensitive scintillator detectors. In addition to sensors for measuring radiation flux, new sensor materials have been developed which are capable of measuring weight, temperature, and source location. An example of a passive sensor for temperature measurement is the combination of a thermophosphor (e.g., rare-earth activated Y 2 O 3 ) with 6 LiF (95% 6 Li). This combination results in a new class of scintillators for thermal neutrons that absorb energy from the radiation particles and remit the energy as a light pulse, the decay rate of which, over a specified temperature range, is temperature dependent. Other passive sensors being developed include pressure-sensitive triboluminescent materials, weight-sensitive silicone rubber fibers, scintillating fibers, and other materials for gamma and neutron detection. The light from the scintillator materials of each sensor would be sent through optical fibers to a monitoring station, where the attribute quantity could be measured and compared with previously recorded emission levels. Confirmatory measurement applications of these technologies are being evaluated to reduce the effort, costs, and employee exposures associated with inventorying stockpiles of highly enriched uranium at the Oak Ridge Y-12 Plant

  17. 78 FR 38739 - Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants

    Science.gov (United States)

    2013-06-27

    ... Systems for Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Regulatory guide; issuance... Guide (RG) 5.29, ``Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants... material control and accounting. This guide applies to all nuclear power plants. ADDRESSES: Please refer to...

  18. Structural materials for innovative nuclear systems (SMINS)

    International Nuclear Information System (INIS)

    2008-01-01

    Structural materials research is a field of growing relevance in the nuclear sector, especially for the different innovative reactor systems being developed within the Generation IV International Forum (GIF), for critical and subcritical transmutation systems, and of interest to the Global Nuclear Energy Partnership (GNEP). Under the auspices of the NEA Nuclear Science Committee (NSC) the Workshop on Structural Materials for Innovative Nuclear Systems (SMINS) was organised in collaboration with the Forschungszentrum Karlsruhe in Germany. The objectives of the workshop were to exchange information on structural materials research issues and to discuss ongoing programmes, both experimental and in the field of advanced modelling. These proceedings include the papers and the poster session materials presented at the workshop, representing the international state of the art in this domain. (author)

  19. A study of total measurement error in tomographic gamma scanning to assay nuclear material with emphasis on a bias issue for low-activity samples

    International Nuclear Information System (INIS)

    Burr, T.L.; Mercer, D.J.; Prettyman, T.H.

    1998-01-01

    Field experience with the tomographic gamma scanner to assay nuclear material suggests that the analysis techniques can significantly impact the assay uncertainty. For example, currently implemented image reconstruction methods exhibit a positive bias for low-activity samples. Preliminary studies indicate that bias reduction could be achieved at the expense of increased random error variance. In this paper, the authors examine three possible bias sources: (1) measurement error in the estimated transmission matrix, (2) the positivity constraint on the estimated mass of nuclear material, and (3) improper treatment of the measurement error structure. The authors present results from many small-scale simulation studies to examine this bias/variance tradeoff for a few image reconstruction methods in the presence of the three possible bias sources

  20. Nuclear technology and materials science

    International Nuclear Information System (INIS)

    Olander, D.R.

    1992-01-01

    Current and expected problems in the materials of nuclear technology are reviewed. In the fuel elements of LWRs, cladding waterside corrosion, secondary hydriding and pellet-cladding interaction may be significant impediments to extended burnup. In the fuel, fission gas release remains a key issue. Materials issues in the structural alloys of the primary system include stress-corrosion cracking of steel, corrosion of steam generator tubing and pressurized thermal shock of the reactor vessel. Prediction of core behavior in severe accidents requires basic data and models for fuel liquefaction, aerosol formation, fission product transport and core-concrete interaction. Materials questions in nuclear waste management and fusion technology are briefly reviewed. (author)

  1. Concerning major items in government ordinance requiring modification of part of enforcement regulation for law relating to control of nuclear material, nuclear fuel and nuclear reactor

    International Nuclear Information System (INIS)

    1989-01-01

    The report describes major items planned to be incorporated into the enforcement regulations for laws relating to control of nuclear material, nuclear fuel and nuclear reactor. The modifications have become necessary for the nation to conclude a nuclear material protection treaty with other countries. The modification include the definitions of 'special nuclear fuel substances' and 'special nuclear fuel substances' and 'special nuclear fuel substances subject to protection'. The modifications require that protective measures be taken when handling and transporting special nuclear fuel substances subject to protection. Transport of special nuclear fuel substances requires approval from the Prime Minister or Transport Minister. Transport of special nuclear fuel substances subject to protection should be conducted after notifying the prefectural Public Safety Commission. Transport of special nuclear fuel substances subject to protection requires the conclusion of arrangements among responsible persons and approval of them from the Prime Minister. (N.K.)

  2. Application of near real time accountancy to nuclear material balance data

    International Nuclear Information System (INIS)

    Seifert, R.

    1990-02-01

    The application of near real time accountancy to nuclear material balance data can be performed effectively only with the help of computerised nuclear material accounting and information systems. Two computer programmes are introduced: DIDI, a programme for computing the MUF series and the measurement model of a reprocessing plant which is assumed to be a one-block model from data resulting from the routine operation of the facility, and PROSA, a programme for statistical analysis of NRTA data, which evaluates the MUF series on the basis of the measurement model. After the presentation of the two computer programmes two examples with realistic balance data will demonstrate the application of NRTA measures. Furthermore, some new remarks on the precision of Monte-Carlo simulations are mentioned which provide a substantial better estimation. (orig.) [de

  3. Audit Report on 'The Department's Management of Nuclear Materials Provided to Domestic Licensees'

    International Nuclear Information System (INIS)

    2009-01-01

    findings and conclusions based on our audit objectives. The audit included tests of controls and compliance with laws and regulations related to managing the Department-owned nuclear materials provided to non-Departmental domestic licensees. Because our review was limited it would not necessarily have disclosed all internal control deficiencies that may have existed at the time of our audit. We examined the establishment of performance measures in accordance with Government Performance and Results Act of 1993, as they related to the audit objective. We found that the Department had established performance measures related to removing or disposing of nuclear materials and radiological sources around the world. We utilized computer generated data during our audit and performed procedures to validate the reliability of the information as necessary to satisfy our audit objective. As noted in the report, we questioned the reliability of the NMMSS data.

  4. International dimension of illicit trafficking in nuclear and other radioactive material

    International Nuclear Information System (INIS)

    Zaitseva, L.; Bunn, G.; Steinhaeusler, F.

    2002-01-01

    Full text: Illicit trafficking in nuclear and other radioactive material is primarily associated with Russia and other former Soviet republics. Indeed, with the collapse of the former Soviet Union (FSU) in 1991, hundreds of tons of weapons-usable nuclear material and thousands of radiation sources were left without adequate control and protection, thus posing a risk for sabotage, theft and diversion. Out of 700 illicit trafficking incidents recorded in the Stanford's database on nuclear smuggling, theft and orphan radiation sources (DSTO), over 450 either took place in the former Soviet Union or involved material that had reportedly originated from the FSU. In the period 1992-1994, Western and Eastern Europe were heavily affected by the inflow of nuclear material smuggled from the FSU. Since then, various measures were taken by the European countries and former Soviet republics to prevent the trafficking of radioactive substances ranging from the improvement of physical security at nuclear facilities to the installation of detection equipment at international borders. However, although the number of illicit trafficking incidents in Western Europe has decreased dramatically since 1994 and the overall annual number of such cases has been lower than in 1994, evidence suggests that diverted nuclear material is still being smuggled out of the FSU. An increased number of interceptions of nuclear and other radioactive material in the Caucasus, Turkey and Central Asia, well-known for their drugs and arms smuggling routes, over the past three years demonstrates that the material may now be moving south rather than west. This is particularly alarming considering the proximity of three countries to the potential end-users of nuclear and other radioactive material, such as AI Qaida terrorist network and aspiring nuclear weapon states in the Middle East. Although the FSU remains the major potential source of nuclear and other radioactive material, it is not the only one. Thefts

  5. New challenges in nuclear material detection

    International Nuclear Information System (INIS)

    Dunlop, W.; Sale, K.; Dougan, A.; Luke, J.; Suski, N.

    2002-01-01

    Full text: Even before the attacks of September 11, 2001 the International Safeguards community recognized the magnitude of the threat posed by illicit trafficking of nuclear materials and the need for enhanced physical protection. For the first time, separate sessions on illicit trafficking and physical protection of nuclear materials were included in the IAEA Safeguards Symposium. In the aftermath of September 11, it is clear that the magnitude of the problem and the urgency with which it must be addressed will be a significant driver for advanced nuclear materials detection technologies for years to come. Trafficking in nuclear material and other radioactive sources is a global concern. According to the IAEA Illicit Trafficking Database Program, there have been confirmed cases in more than 40 countries and the number of cases per year have nearly doubled since 1996. The challenge of combating nuclear terrorism also brings with it many opportunities for the development of new tools and new approaches. In addition to the traditional gamma-ray imaging, spectrometry and neutron interrogation, there is a need for smaller, smarter, more energy-efficient sensors and sensor systems for detecting and tracking threats. These systems go by many names - correlated sensor networks, wide-area tracking systems, sensor or network fabrics - but the concept behind them is the same. Take a number of wireless sensors and tie them together with a communications network, develop a scheme for fusing the data and make the system easy to deploy. This paper will present a brief survey of nuclear materials detection capability, and discuss some advances in research and development that are particularly suited for illicit trafficking, detection of shielded highly enriched uranium, and border security. (author)

  6. Regulations concerning the transport of nuclear fuel materials outside the works or the enterprise

    International Nuclear Information System (INIS)

    1981-01-01

    This rule is established under the provisions of the law concerning the regulation of nuclear raw materials, nuclear fuel materials and nuclear reactors and the ordinance for its execution, and to enforce the law. Basic terms are defined, such as vehicle transport, simplified transport, nuclear fuel transport goods, exclusive loading, worker, cumulative dose and exposure radiation dose. Nuclear fuel transport goods are classified into types of L, A, BM and BU according to their radioactivities. Radiation dose rate shall not exceed 0.5 milli-rem an hour on the surface of the type L, and 200 milli-rem an hour on the surface of the type A. For the type BM, the rate shall not surpass 1,000 milli-rem an hour at the distance of 1 meter from the surface in the special test conditions. The transport goods of fissile materials must not reach criticality on the way, but also shall conform to the stipulated technical standards. The particular things contaminated by nuclear fuel materials can be transported without specifying as nuclear fuel transport goods, and their radiation dose rate shall not go beyond 0.5 milli-rem an hour on the surface. The transport by special measures, the technical standards of simplified transport and measures to be taken in danger in transit are defined, respectively.(Okada, K.)

  7. International training course on nuclear materials accountability for safeguards purposes

    International Nuclear Information System (INIS)

    1980-12-01

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

  8. International training course on nuclear materials accountability for safeguards purposes

    Energy Technology Data Exchange (ETDEWEB)

    1980-12-01

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

  9. Welcome from INMM (Institute of Nuclear Materials Management)

    International Nuclear Information System (INIS)

    Satkowiak, L.

    2015-01-01

    The Institute of Nuclear Materials Management (INMM) is the premier professional society focused on safe and secure use of Nuclear Materials and the related nuclear scientific technology and knowledge. Its international membership includes government, academia, non-governmental organizations and industry, spanning the full spectrum all the way from policy to technology. The Institute's primary role include the promotion of research, the establishment of standards and the development of best practices, all centered around nuclear materials. It then disseminates this information through meetings, professional contacts, reports, papers, discussions, and publications. The formal structure of the INMM includes six technical divisions: Facility Operation; Materials Control and Accountability; Nonproliferation and Arms Control; Nuclear Security and Physical Protection; Packaging, Transportation and Disposition

  10. Detecting Illicit Nuclear Materials

    International Nuclear Information System (INIS)

    Kouzes, Richard T.

    2005-01-01

    The threat that weapons of mass destruction might enter the United States has led to a number of efforts for the detection and interdiction of nuclear, radiological, chemical, and biological weapons at our borders. There have been multiple deployments of instrumentation to detect radiation signatures to interdict radiological material, including weapons and weapons material worldwide

  11. Experience in nuclear materials accountancy, including the use of computers, in the UKAEA

    International Nuclear Information System (INIS)

    Anderson, A.R.; Adamson, A.S.; Good, P.T.; Terrey, D.R.

    1976-01-01

    The UKAEA have operated systems of nuclear materials accountancy in research and development establishments handling large quantities of material for over 20 years. In the course of that time changing requirements for nuclear materials control and increasing quantities of materials have required that accountancy systems be modified and altered to improve either the fundamental system or manpower utilization. The same accountancy principles are applied throughout the Authority but procedures at the different establishments vary according to the nature of their specific requirements; there is much in the cumulative experience of the UKAEA which could prove of value to other organizations concerned with nuclear materials accountancy or safeguards. This paper reviews the present accountancy system in the UKAEA and summarizes its advantages. Details are given of specific experience and solutions which have been found to overcome difficulties or to strengthen previous weak points. Areas discussed include the use of measurements, the establishment of measurement points (which is relevant to the designation of MBAs), the importance of regular physical stock-taking, and the benefits stemming from the existence of a separate accountancy section independent of operational management at large establishments. Some experience of a dual system of accountancy and criticality control is reported, and the present status of computerization of nuclear material accounts is summarized. Important aspects of the relationship between management systems of accountancy and safeguards' requirements are discussed briefly. (author)

  12. Resources of nuclear fuels and materials

    Energy Technology Data Exchange (ETDEWEB)

    Kawamura, K [Tokyo Inst. of Tech. (Japan); Kamiyama, Teiji; Hayashi, S; Hida, Noboru; Okano, T

    1974-11-01

    In this explanatory article, data on the world resources of nuclear fuels and materials, their production, and the present state of utilization are presented by specialists in varied fields. Main materials taken up are uranium, thorium, beryllium, zirconium, niobium, rare earth elements, graphite, and materials for nuclear fusion (heavy hydrogen and tritium). World reserves and annual production of these materials listed in a number of tables are cited from statistics of the period 1970-1973 or given by estimation. These data may be used as valuable numerical data for various projects and problems of atomic power industries.

  13. Strategic special nuclear material Inventory Differences. Semiannual report, April 1-September 30, 1984

    International Nuclear Information System (INIS)

    1985-07-01

    This sixteenth periodic semiannual report of Inventory Differences (ID) covers the last six months of fiscal year 1984 (April 1, 1984, through September 30, 1984), for the Department of Energy (DOE) and DOE contractor facilities possessing significant quantities of strategic special nuclear material (SSNM). Inventory Differences are simply the differences between the amount of material shown in the accounting records and the amount of material reported in the physical inventory. These differences are generally due to errors in estimating material in unmeasurable form at the time of an inventory, unmeasurable holdup in equipment, measurement imprecisions, inaccuracies in initial determinations of SSNM produced or used in nuclear reactors, and inventory or bookkeeping errors. Both DOE and contractors operating DOE facilities carefully maintain, analyze, and investigate ID data. Inventory Differences are expected in nuclear material processing and are not, in and of themselves, evidence of lost or stolen material. On the other hand, ID analysis provides valuable information on the effectiveness of the safeguards system's physical protection and material control measures as well as a check on the process controls and material management procedures. ID's outside safeguards control limits or involving a missing SSNM discrete item are investigated. If necessary, an operation may be shut down until an ID is resolved

  14. The national nuclear material tracking system. A Korea's countermeasure against nuclear terrorism

    International Nuclear Information System (INIS)

    Moon, Joo Hyun

    2011-01-01

    Since nuclear terrorism has been identified as a real threat, the Korean government has earnestly developed elementary technologies and sub-systems for establishing an integrated defensive system against nuclear terrorism, which is based on the concept of defense-in-depth. This paper introduces the gist and implications of the studies that have been conducted in building the national nuclear material tracking system for preventing and intercepting the illicit trafficking and transporting of nuclear material in Korea. (orig.)

  15. Current trends in nuclear material transportation

    International Nuclear Information System (INIS)

    Ravenscroft, Norman; Oshinowo, Franchone

    1997-01-01

    The business of radioactive material transportation has evolved considerably in the past 40 years. Current practices reflect extensive international experience in handling radioactive cargo within a mature and tested regulatory framework. Nevertheless, new developments continue to have an impact on how shipments of nuclear material are planned and carried out. Entities involved in the transport of radioactive materials must keep abreast of these developments and work together to find innovative solutions to ensure that safe, smooth transport activities may continue. Several recent trends in the regulatory environment and political atmosphere require attention. There are four key trends that we'll be examining today: 1) the reduction in the pool of available commercial carriers; 2) routing restrictions; 3) package validation issues; and 4) increasing political sensitivities. Careful planning and cooperative measures are necessary to alleviate problems in each of these areas. (author)

  16. Order for execution of the law concerning regulations of nuclear source materials, nuclear fuel materials and reactors

    International Nuclear Information System (INIS)

    1978-01-01

    Under the above mentioned law this order prescribes the procedures of controls given to the persons who wish to conduct refining and fabricating businesses, to construct and operate reactors, and to use nuclear source materials, nuclear fuel materials and internationally controlled materials. The common controlling principle prescribed is that the permission or authorization necessary for above listed businesses should be applied for at each factory or each place of business. Based on the principle, the order prescribes: the procedures to apply for the authorization of the refining business, the permission of the change thereof, and the permission of the fabricating business and the change, thereof (the 1st chapter); the procedures to apply for the permission of the construction of reactors and of the change of the construction, as well as the procedure to do periodic inspections of reactor facilities (the 2nd chapter); the procedures to apply for the permission to use nuclear fuel materials and to change the use thereof, the submission of the report to use nuclear source materials, as well as the procedure to apply for the permission to use internationally controlled materials. In the 4th chapter the order lists up the items on which the competent Ministers may require reports from the person who carries on the relevant business. (Matsushima, A.)

  17. Nuclear material discovery or loss: the French experience

    International Nuclear Information System (INIS)

    Zanetti, S.H.

    2006-01-01

    In a nuclear facility, when a difference between the physical inventory listing and accountancy records is discovered, the French law (Article 11 of the 'Decret 81-512') requires a declaration to the High Civil Servant for Defence of the Ministry in charge of Industry. Moreover, according to article L.1333-13 of the Defence Code, in case of a suspicion of loss, theft or diversion of nuclear material, the licensee has to declare this event to the police. In the meantime, an investigation is carried out in the facility, and in cooperation with other facilities if necessary. These measures are aimed at: - Finding the lost nuclear material (if any), - Understand the causes of the problem, - Solve the differences by acting on the PIL or/and accountancy records, - Act to prevent any other occurrence of this kind of event. These actions can take place in the general field of a police investigation. After all these facts and information have been gathered, the licensee writes down a complete file which is transferred to the High Civil Servant for Defence of the Ministry in charge of Industry, in order to be analysed by his technical support body (IRSN). Thus, the IRSN is able to give its conclusion to the authority about this event, especially regarding: - The causes of the event, - Relevance and completeness of investigations, - Pertinence of the corrections, - Relevance of corrective actions, - Probability of another occurrence. This system is useful to ensure a complete follow-up of the events occurring in the various nuclear facilities in France, to have an extensive overview of the problems on a national scale. If an item is found in a facility A, numerous questions must be answered: - Where does it come from? - Since when is it in facility A? - How did it happened that this item has been transferred from facility B to facility A without the transfer of information? - We will consider these issues through examples. This kind of event can be potentially very rich in

  18. Nuclear material control and accountancy planning and performance testing

    International Nuclear Information System (INIS)

    Mike Enhinger; Dennis Wilkey; Rod Martin; Ken Byers; Brian Smith

    1999-01-01

    An overview of performance testing as used at U.S. Department of Energy facilities is provided. Performance tests are performed on specific aspects of the regulations or site policy. The key issues in establishing a performance testing program are: identifying what needs to be tested; determining how to test; establishing criteria to evaluate test results. The program elements of performance testing program consist of: planning; coordination; conduct; evaluation. A performance test may be conducted of personnel or equipment. The DOE orders for nuclear material control and accountancy are divided into three functional areas: program administration, material accounting, and material control. Examples performance tests may be conducted on program administration, accounting, measurement and measurement control, inventory, and containment [ru

  19. Nuclear materials transportation

    International Nuclear Information System (INIS)

    Ushakov, B.A.

    1986-01-01

    Various methods of nuclear materials transportation at different stages of the fuel cycle (U 3 O 8 , UF 6 production enrichment, fuel element manufacturing, storage) are considered. The advantages and drawbacks of railway, automobile, maritime and air transport are analyzed. Some types of containers are characterized

  20. Achievements and questions in the accountability of nuclear materials and their verification for safeguards purposes

    International Nuclear Information System (INIS)

    Deron, S.

    1990-01-01

    A very accurate accountability of nuclear materials is required throughout the industrial nuclear fuel cycle for technical reasons and safety purposes but also for commercial, physical protection and safeguards objectives. The present note intends to illustrate with a few samples the performance presently achieved and the major questions which the analysts are facing in these areas. The examples taken concern the accountability of feed and product materials at LWR nuclear fuel fabrication plants and spent fuel reprocessing plants. They were selected because they constitute major components of the flow and inventory of the nuclear fuel materials at key measurement points in nuclear industry. The factors limiting the quality of the assays and accountability of these industrial materials and some observations regarding the need and use of reference materials and quality control programmes in support of accurate accounting are presented. 7 refs

  1. Evaluation of Terminated Nuclear Material Licenses

    International Nuclear Information System (INIS)

    Spencer, K.M.; Zeighami, E.A.

    1999-01-01

    This report presents the results of a six-year project that reviewed material licenses that had been terminated during the period from inception of licensing until approximately late-1994. The material licenses covered in the review project were Part 30, byproduct material licenses; Part 40, source material licenses; and Part 70, special nuclear material licenses. This report describes the methodology developed for the project, summarizes the findings of the license file inventory process, and describes the findings of the reviews or evaluations of the license files. The evaluation identified nuclear material use sites that need review of the licensing material or more direct follow-up of some type. The review process also identified licenses authorized to possess sealed sources for which there was incomplete or missing documentation of the fate of the sources

  2. Nuclear moments as a probe of electronic structure in material, exotic nuclear structure and fundamental symmetry

    Energy Technology Data Exchange (ETDEWEB)

    Matsuta, K., E-mail: matsuta@vg.phys.sci.osaka-u.ac.jp; Minamisono, T.; Mihara, M.; Fukuda, M. [Osaka Univ., Dept. of Physics (Japan); Zhu, Shengyun [CIAE (China); Masuda, Y. [High Energy Accelerator Research Organization (KEK) (Japan); Hatanaka, K. [Osaka Univ., RCNP (Japan); Yuan Daqing; Zheng Yongnan; Zuo Yi; Fang Ping; Zhou Dongmei [CIAE (China); Ohtsubo, T. [Niigata Univ., Dept. of Physics (Japan); Izumikawa, T. [Niigata Univ., RI Center (Japan); Momota, S. [Kochi Univ. of Technology (Japan); Nishimura, D. [Tokyo Univ. of Science (Japan); Matsumiya, R. [Osaka Univ., RCNP (Japan); Kitagawa, A.; Sato, S.; Kanazawa, M. [Nat. Inst. Radiological Sciences (Japan); Collaboration: Osaka-CIAE-NIRS-Niigata-Kochi-LBL Collaboration; and others

    2013-05-15

    We report our studies in various fields of Physics through nuclear moments utilizing the {beta}-NMR technique, including material sciences, nuclear structures and fundamental symmetries. Especially, we focus on the recent progress in the studies on the electronic structure in Pt through Knight shifts of various impurities, lattice locations of impurities, electric field gradients, the analysis of nuclear spin in terms of its components, anomaly in the spin expectation value for {sup 9}C-{sup 9}Li mirror pair, the G-parity conservation law, and the Ramsey resonance on UCN for future neutron EDM measurements.

  3. Materials. The Argentine nuclear policy

    International Nuclear Information System (INIS)

    Strasser, H.

    1982-01-01

    Part A of the volume contains a literature search on proliferation and the Third World and on the nuclear technology of Argentina. The materials in part B are divided in: 1. Nonproliferation discussion and the Third World. 2. Development and state of nuclear technology in Argentina. 3. Argentina's international contacts in the field of nuclear energy 1. Federal Republic of Germany, 2. Soviet Union, 3. Brazil. (orig./HP) [de

  4. The establishment of computer system for nuclear material accounting

    International Nuclear Information System (INIS)

    Hong, Jong Sook; Lee, Byung Doo; Park, Ho Joon

    1988-01-01

    Computer based nuclear material accountancy system will not only increase the credibility of KOREA-IAEA safeguards agreement and bilateral agreements but also decrease the man-power needed to carry out the inspection activity at state level and at facility level. Computer software for nuclear material accounting for and control has been materialized the application to both item and bulk facilities and software for database at state level has been also established to maintain up -to-date status of nation-wide nuclear material inventory. Computer recordings and reporting have been realized to fulfill the national and international commitments to nuclear material accounting for and control. The exchange of information related to nuclear material accounting for has become possible by PC diskettes. (Author)

  5. A future vision of nuclear material information systems

    International Nuclear Information System (INIS)

    Suski, N.; Wimple, C.

    1999-01-01

    To address the current and future needs for nuclear materials management and safeguards information, Lawrence Livermore National Laboratory envisions an integrated nuclear information system that will support several functions. The vision is to link distributed information systems via a common communications infrastructure designed to address the information interdependencies between two major elements: Domestic, with information about specific nuclear materials and their properties, and International, with information pertaining to foreign nuclear materials, facility design and operations. The communication infrastructure will enable data consistency, validation and reconciliation, as well as provide a common access point and user interface for a broad range of nuclear materials information. Information may be transmitted to, from, and within the system by a variety of linkage mechanisms, including the Internet. Strict access control will be employed as well as data encryption and user authentication to provide the necessary information assurance. The system can provide a mechanism not only for data storage and retrieval, but will eventually provide the analytical tools necessary to support the U.S. government's nuclear materials management needs and non-proliferation policy goals

  6. NMR dispersion measurement of dynamic nuclear polarization

    International Nuclear Information System (INIS)

    Davies, K.; Cox, S.F.J.

    1978-01-01

    The feasibility of monitoring dynamic nuclear polarization from the NMR dispersive susceptibility is examined. Two prototype instruments are tested in a polarized proton target using organic target material. The more promising employs a tunnel diode oscillator, inside the target cavity, and should provide a precise polarization measurement working at a frequency far enough from the main resonance for the disturbance of the measured polarization to be negligible. Other existing methods for measuring target polarization are briefly reviewed. (author)

  7. A review on nuclear forensic methodology for analysis of nuclear material of unknown origin

    International Nuclear Information System (INIS)

    Deshmukh, A.V.; Raghav, N.K.; Fatangare, N.M.; Jagtap, S.S.

    2014-01-01

    With the growing use of nuclear power and threat from illegal nuclear smuggling nuclear forensic provides an aid to the law enforcement to trace back modus operandi of such threats. Extensive nuclear proliferation, race among countries to acquire nuclear capability and global terrorism scenario has mandated Nuclear Forensic Science technology to tackle nuclear threats. Gamma spectrometry, alpha spectrometry, thermal ionization mass spectrometry, inductively coupled plasma mass spectrometry are employed for characterization and relative isotopic composition determinant of Nuclear material and techniques like SEM transmission electron TEM, FT-IR, GC-MS, Electrophoretic technique are used to characterize the contaminated materials in order to deceive investigative agencies. The present paper provide systematic forensic methodology for nuclear and radioactive materials encountered at any crime scene due to any accidental discharges or military activities. (author)

  8. Strengthening global practices for protecting nuclear material (NUMAT). Book of Abstracts

    International Nuclear Information System (INIS)

    Steinhaeusler, F.; Heissl, C.

    2002-08-01

    The International Conference on Physical Protection 'Strengthening Global Practices for Protecting Nuclear Material' was organized by the Institute of Physics and Biophysics, Salzburg University in cooperation with/supported by the European Commission, Lawrence Livermore National Laboratory, European Forum of the Stanford University's Institute for International Studies and Austria Institute for European Security. Its purpose was fostering exchange of information on the policy and technical aspects require to ensure the security of nuclear material around the world. There is a general concern that the international community needs to establish effective measures to counter theft, sabotage, and other illicit uses of nuclear fissile and other radioactive materials. The main subjects addressed by this conference were: a) global and local threat development and 'design basis'; b) standards for physical protection (PP), its adequacy and future needs; c) national practices in PP of nuclear materials (how to strengthen national security culture?); d) current R and D in security and detection technologies (identification of focus points for future R and D); e) programmes to aid in training, design, and implementation of physical protection systems (how to improve efficiency and assure sustainability of assistance programmes?). (nevyjel)

  9. Proposal for guidelines for the physical protection of nuclear materials, plants and transports in Denmark

    International Nuclear Information System (INIS)

    1978-03-01

    The guidelines are based on recommendations in the IAEA's ''Physical Protection of Nuclear Material,'' INFCIRC/225/rev.1. In accordance with practice in other countries, the guidelines give more detailed requirements for the protection of reactor plants than those given in the IAEA's present recommendations, which put more emphasis on the protection of nuclear materials. The measures to be taken for nuclear plants, or nuclear transports, are proposed made to fit the potential risk that the more closely defined actions imply. It is suggested that the more detailed rules for the scope of the protection of plants or materials should be laid down by the National Agency on the basis of recommendations made by the Inspectorate of Nuclear Installations, which in turn are based on the safety documentation of the plant/material owners. It is further proposed that the National Agency, again on a recommendation from the Inspectorate, should lay down more detailed guidelines for the reporting of changes in stocks or transports of nuclear materials. (author)

  10. Material control in nuclear fuel fabrication facilities. Part II. Accountability, instrumntation, and measurement techniques in fuel fabrication facilities, P.O.1236909. Final report

    International Nuclear Information System (INIS)

    Borgonovi, G.M.; McCartin, T.J.; McDaniel, T.; Miller, C.L.; Nguyen, T.

    1978-12-01

    This report describes the measurement techniques, the instrumentation, and the procedures used in accountability and control of nuclear materials, as they apply to fuel fabrication facilities. Some of the material included has appeared elswhere and it has been summarized. An extensive bibliography is included. A spcific example of application of the accountability methods to a model fuel fabrication facility which is based on the Westinghouse Anderson design

  11. Material control in nuclear fuel fabrication facilities. Part II. Accountability, instrumntation, and measurement techniques in fuel fabrication facilities, P. O. 1236909. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Borgonovi, G.M.; McCartin, T.J.; McDaniel, T.; Miller, C.L.; Nguyen, T.

    1978-12-01

    This report describes the measurement techniques, the instrumentation, and the procedures used in accountability and control of nuclear materials, as they apply to fuel fabrication facilities. Some of the material included has appeared elswhere and it has been summarized. An extensive bibliography is included. A spcific example of application of the accountability methods to a model fuel fabrication facility which is based on the Westinghouse Anderson design.

  12. Tungsten - Yttrium Based Nuclear Structural Materials

    Science.gov (United States)

    Ramana, Chintalapalle; Chessa, Jack; Martinenz, Gustavo

    2013-04-01

    The challenging problem currently facing the nuclear science community in this 21st century is design and development of novel structural materials, which will have an impact on the next-generation nuclear reactors. The materials available at present include reduced activation ferritic/martensitic steels, dispersion strengthened reduced activation ferritic steels, and vanadium- or tungsten-based alloys. These materials exhibit one or more specific problems, which are either intrinsic or caused by reactors. This work is focussed towards tungsten-yttrium (W-Y) based alloys and oxide ceramics, which can be utilized in nuclear applications. The goal is to derive a fundamental scientific understanding of W-Y-based materials. In collaboration with University of Califonia -- Davis, the project is designated to demonstrate the W-Y based alloys, ceramics and composites with enhanced physical, mechanical, thermo-chemical properties and higher radiation resistance. Efforts are focussed on understanding the microstructure, manipulating materials behavior under charged-particle and neutron irradiation, and create a knowledge database of defects, elemental diffusion/segregation, and defect trapping along grain boundaries and interfaces. Preliminary results will be discussed.

  13. A survey of infrared technology for special nuclear materials control and accounting

    International Nuclear Information System (INIS)

    Stanbro, W.D.; Leonard, R.S.; Steverson, C.A.; Angerman, M.I.

    1992-03-01

    This report reviews some aspects of current infrared measurement technology and suggests two applications in which it may be used in nuclear safeguards. These applications include both materials control and materials accounting. In each case, the measurements rely on passive detection of infrared radiation generated from the heat produced by the radioactive decay of plutonium. Both imaging and non-imaging techniques are discussed

  14. From nuclear installation to greenfield site. SCK-CEN develops a new measurement method

    International Nuclear Information System (INIS)

    2014-01-01

    The article discusses a new measurement method that has been developed by the Belgian Nuclear Research Center SCK-CEN in conjunction with the decommissioning of nuclear facilities. This measurement technique is based on on-site gamma ray spectrometry in combination with modelling and is employed for directing the flow of demolition materials in the decommissioning of nuclear facilities.

  15. Legal framework and practice to prevent and detect illicit trafficking of nuclear and radioactive materials

    International Nuclear Information System (INIS)

    Sembiring, D.

    2001-01-01

    Full text: Illicit trafficking in nuclear and radioactive materials in the country and across country borders has become serious problem from both nuclear proliferation and radiological hazard point of view. Prevention and detection of illicit trafficking in nuclear and radioactive materials is based on the regulation and procedure set up to ensure the control of the nuclear and radioactive materials throughout their life. Practically, prevention and detection measures in ensuring that nuclear materials do not become the subject of unauthorized use leading to illicit trafficking constitute (1) accounting for and (2) control of nuclear and radioactive materials and (3) physical protection of such materials. The Nuclear Energy Act No. 10 year 1997 is the legislative basis for the safety, including nuclear material accounting and control activities as well as security measures on the utilization of the nuclear and radioactive material in Indonesia. Government establishes Nuclear Energy Control Board (BAPETEN) as Regulatory Body having the task to control any activities using nuclear energy. The activities of control are implemented through regulation, licensing and inspection. The mission of the BAPETEN is to ensure adequate protection of the public health and safety, the common security, and the environmental in the peaceful uses of nuclear energy in Indonesia. To support this mission, BAPETEN has three principal regulatory functions: (1) establish regulation; (2) issue licenses and (3) inspect nuclear facilities. First component of regulatory function is establishing regulations, which define the capabilities that need to be satisfied by facility operators to protect against theft which in turn could lead to illicit trafficking. BAPETEN established the Decree on National System of Accounting for and Control of Nuclear Material (SSAC) based on the Agreement between Rl and IAEA on the Application of Safeguards in connection with NPT ratified in the Act No.8 year 1978

  16. Rattling nucleons: New developments in active interrogation of special nuclear material

    International Nuclear Information System (INIS)

    Runkle, Robert C.; Chichester, David L.; Thompson, Scott J.

    2012-01-01

    Active interrogation is a vigorous area of research and development due to its promise of offering detection and characterization capabilities of special nuclear material in environments where passive detection fails. The primary value added by active methods is the capability to penetrate shielding - special nuclear material itself, incidental materials, or intentional shielding - and advocates hope that active interrogation will provide a solution to the problem of detecting shielded uranium, which is at present the greatest obstacle to interdiction efforts. The technique also provides a unique benefit for quantifying nuclear material in high background-radiation environments, an area important for nuclear material safeguards and material accountancy. Progress has been made in the field of active interrogation on several fronts, most notably in the arenas of source development, systems integration, and the integration and exploitation of multiple fission and non-fission signatures. But penetration of interrogating radiation often comes at a cost, not only in terms of finance and dose but also in terms of induced backgrounds, system complexity, and extended measurement times (including set up and acquisition). These costs make the calculus for deciding to implement active interrogation more subtle than may be apparent. The purpose of this review is thus to examine existing interrogation methods, compare and contrast their attributes and limitations, and identify missions where active interrogation may hold the most promise.

  17. Order for execution of the law concerning regulations of nuclear source materials, nuclear fuel materials and reactors

    International Nuclear Information System (INIS)

    1985-01-01

    This ordinance is stipulated under the law concerning the regulation of nuclear raw materials, nuclear fuel materials and reactors. The designation for refining and processing businesses under the law shall be obtained for each works or enterprise where these operations are to be practiced. Persons who intend to accept the designation shall file applications attaching business plans and the other documents specified by the ordinances of the Prime Minister's Office and other ministry orders. The permission for the installation of nuclear reactors under the law shall be received for each works or enterprise where reactors are to be set up. Persons who intend to get the permission shall file applications attaching the financing plans required for the installation of reactors and the other documents designated by the orders of the competent ministry. The permission concerning the reactors installed on foreign ships shall be obtained for each ship which is going to enter into the Japanese waters. Persons who ask for the permission shall file applications attaching the documents which explain the safety of reactor facilities and the other documents defined by the orders of the Ministry of Transportation. The designation for reprocessing business and the application for it are provided for, respectively. The usage of nuclear fuel materials, nuclear raw materials and internationally regulated goods is ruled in detail. (Kubozone, M.)

  18. Order for execution of the law concerning regulations of nuclear source materials, nuclear fuel materials and reactors

    International Nuclear Information System (INIS)

    1981-01-01

    This ordinance is stipulated under the law concerning the regulation of nuclear raw materials, nuclear fuel materials and reactors. The designation for refining and processing businesses under the law shall be obtained for each works or enterprise where these operations are to be practiced. Persons who intend to accept the designation shall file applications attaching business plans and the other documents specified by the ordinances of the Prime Minister's Office and other ministry orders. The permission for the installation of nuclear reactors under the law shall be received for each works or enterprise where reactors are to be set up. Persons who intend to get the permission shall file applications attaching the financing plans required for the installation of reactors and the other documents designated by the orders of the competent ministry. The permission concerning the reactors installed on foreign ships shall be obtained for each ship which is going to enter into the Japanese waters. Persons who ask for the permission shall file applications attaching the documents which explain the safety of reactor facilities and the other documents defined by the orders of the Ministry of Transportation. The designation for reprocessing business and the application for it are provided for, respectively. The usage of nuclear fuel materials, nuclear raw materials and internationally regulated goods is ruled in detail.(Okada, K.)

  19. RADIATION EFFECTS IN NUCLEAR WASTE MATERIALS

    International Nuclear Information System (INIS)

    Weber, William J.

    2000-01-01

    The objective of this research was to develop fundamental understanding and predictive models of radiation effects in glasses and ceramics at the atomic, microscopic, and macroscopic levels, as well as an understanding of the effects of these radiation-induced solid-state changes on dissolution kinetics (i.e., radionuclide release). The research performed during the duration of this project has addressed many of the scientific issues identified in the reports of two DOE panels [1,2], particularly those related to radiation effects on the structure of glasses and ceramics. The research approach taken by this project integrated experimental studies and computer simulations to develop comprehensive fundamental understanding and capabilities for predictive modeling of radiation effects and dissolution kinetics in both glasses and ceramics designed for the stabilization and immobilization of high-level tank waste (HLW), plutonium residues and scraps, surplus weapons plutonium, other actinides, and other highly radioactive waste streams. Such fundamental understanding is necessary in the development of predictive models because all experimental irradiation studies on nuclear waste materials are ''accelerated tests'' that add a great deal of uncertainty to predicted behavior because the damage rates are orders of magnitude higher than the actual damage rates expected in nuclear waste materials. Degradation and dissolution processes will change with damage rate and temperature. Only a fundamental understanding of the kinetics of all the physical and chemical processes induced or affected by radiation will lead to truly predictive models of long-term behavior and performance for nuclear waste materials. Predictive models of performance of nuclear waste materials must be scientifically based and address both radiation effects on structure (i.e., solid-state effects) and the effects of these solid-state structural changes on dissolution kinetics. The ultimate goal of this

  20. Combating illicit trafficking in nuclear and other radioactive material. Technical guidance. Reference manual. (Chinese Edition)

    International Nuclear Information System (INIS)

    2012-01-01

    This publication is intended for individuals and organizations that may be called upon to deal with the detection of and response to criminal or unauthorized acts involving nuclear or other radioactive material. It will also be useful for legislators, law enforcement agencies, government officials, technical experts, lawyers, diplomats and users of nuclear technology. This manual emphasizes the international initiatives for improving the security of nuclear and other radioactive material. However, it is recognized that effective measures for controlling the transfer of equipment, non-nuclear material, technology or information that may assist in the development of nuclear explosive devices, improvised nuclear devices (INDs) or other radiological dispersal devices (RDDs) are important elements of an effective nuclear security system. In addition, issues of personal integrity, inspection and investigative procedures are not discussed in this manual, all of which are essential elements for an effective overall security system. The manual considers a variety of elements that are recognized as being essential for dealing with incidents of criminal or unauthorized acts involving nuclear and other radioactive material. Depending on conditions in a specific State, including its legal and governmental infrastructure, some of the measures discussed will need to be adapted to suit that State's circumstances. However, much of the material can be applied directly in the context of other national programmes. This manual is divided into four main parts. Section 2 discusses the threat posed by criminal or unauthorized acts involving nuclear and other radioactive material, as well as the policy and legal bases underlying the international effort to restrain such activities. Sections 3 and 4 summarize the major international undertakings in the field. Sections 5-8 provide some basic technical information on radiation, radioactive material, the health consequences of radiation

  1. Molecular forensic science of nuclear materials

    International Nuclear Information System (INIS)

    Wilkerson, Marianne Perry

    2010-01-01

    We are interested in applying our understanding of actinide chemical structure and bonding to broaden the suite of analytical tools available for nuclear forensic analyses. Uranium- and plutonium-oxide systems form under a variety of conditions, and these chemical species exhibit some of the most complex behavior of metal oxide systems known. No less intriguing is the ability of AnO 2 (An: U, Pu) to form non-stoichiometric species described as AnO 2+x . Environmental studies have shown the value of utilizing the chemical signatures of these actinide oxides materials to understand transport following release into the environment. Chemical speciation of actinide-oxide samples may also provide clues as to the age, source, process history, or transport of the material. The scientific challenge is to identify, measure and understand those aspects of speciation of actinide analytes that carry information about material origin and history most relevant to forensics. Here, we will describe our efforts in material synthesis and analytical methods development that we will use to provide the fundamental science required to characterize actinide oxide molecular structures for forensics science. Structural properties and initial results to measure structural variability of uranium oxide samples using synchrotron-based X-ray Absorption Fine Structure will be discussed.

  2. Survey procedure: Control and accountability of nuclear materials

    International Nuclear Information System (INIS)

    Van Ness, H.

    1987-02-01

    This procedure outlines the method by which the Department of Energy (DOE) San Francisco Operations Office (SAN) will plan and execute periodic field surveys of the Material Control and Accountability (MC and A) program and practices at designated contractors' facilities. The surveys will be conducted in accordance with DOE Order 5630.7, Control and Accountability of Nuclear Materials Surveys (7/8/81) to ascertain compliance with applicable DOE Orders and SAN Management Directives in the 5630 series, as well as the adequacy of the contractor's program and procedures. Surveys will be conducted by the Safeguards and Security Division of DOE-SAN. The survey team will review and evaluate the adequacy of the contractor's procedures and practices for nuclear material control and accounting by means of physical inventory, internal control, measurement and statistics, material control indicators, records and reports, and personnel training. The survey will include an audit of records and reports, observation of inventory procedures, an independent test of the inventory and a review and evaluation of the inventory differences, accidental losses, and normal operational losses as applicable to the facility to be surveyed

  3. Software development for managing nuclear material database

    International Nuclear Information System (INIS)

    Tondin, Julio Benedito Marin

    2011-01-01

    In nuclear facilities, the nuclear material control is one of the most important activities. The Brazilian National Commission of Nuclear Energy (CNEN) and the International Atomic Energy Agency (IAEA), when inspecting routinely, regards the data provided as a major safety factor. Having a control system of nuclear material that allows the amount and location of the various items to be inspected, at any time, is a key factor today. The objective of this work was to enhance the existing system using a more friendly platform of development, through the VisualBasic programming language (Microsoft Corporation), to facilitate the operation team of the reactor IEA-R1 Reactor tasks, providing data that enable a better and prompter control of the IEA-R1 nuclear material. These data have allowed the development of papers presented at national and international conferences and the development of master's dissertations and doctorate theses. The software object of this study was designed to meet the requirements of the CNEN and the IAEA safeguard rules, but its functions may be expanded in accordance with future needs. The program developed can be used in other reactors to be built in the country, since it is very practical and allows an effective control of the nuclear material in the facilities. (author)

  4. Review of fracture properties of nuclear materials determined by Hertzian indentation

    International Nuclear Information System (INIS)

    Routbort, J.; Matzke, H.

    1985-01-01

    A brief description of the determination of the surface fracture energy and the fracture toughness from a Hertzian indentation test is given. A number of theoretical and experimental problems are discussed. Results obtained on a variety of nuclear fuels and nuclear-waste-containment materials are reviewed and compared with values measured by other techniques. The Hertzian indentation test yields reliable fracture parameters

  5. Nuclear Materials Stewardship Within the DOE Environmental Management Program

    International Nuclear Information System (INIS)

    Bilyeu, J. D.; Kiess, T. E.; Gates, M. L.

    2002-01-01

    The Department of Energy (DOE) Environmental Management (EM) Program has made significant progress in planning disposition of its excess nuclear materials and has recently completed several noteworthy studies. Since establishment in 1997, the EM Nuclear Material Stewardship Program has developed disposition plans for excess nuclear materials to support facility deactivation. All nuclear materials have been removed from the Miamisburg Environmental Management Project (Mound), and disposition planning is nearing completion for the Fernald Environmental Management Project and the Rocky Flats Environmental Technology Site. Only a few issues remain for materials at the Hanford and Idaho sites. Recent trade studies include the Savannah River Site Canyons Nuclear Materials Identification Study, a Cesium/Strontium Management Alternatives Trade Study, a Liquid Technical Standards Trade Study, an Irradiated Beryllium Reflectors with Tritium study, a Special Performance Assessment Required Trade Study, a Neutron Source Trade Study, and development of discard criteria for uranium. A Small Sites Workshop was also held. Potential and planned future activities include updating the Plutonium-239 storage study, developing additional packaging standards, developing a Nuclear Material Disposition Handbook, determining how to recover or dispose of Pu-244 and U-233, and working with additional sites to define disposition plans for their nuclear materials

  6. Nuclear instrumentation for the industrial measuring systems

    International Nuclear Information System (INIS)

    Normand, S.

    2010-01-01

    This work deals with nuclear instrumentation and its application to industry, power plant fuel reprocessing plant and finally with homeland security. The first part concerns the reactor instrumentation, in-core and ex-core measurement system. Ionization Uranium fission chamber will be introduced with their acquisition system especially Campbell mode system. Some progress have been done on regarding sensors failure foresee. The second part of this work deals with reprocessing plant and associated instrumentation for nuclear waste management. Proportional counters techniques will be discussed, especially Helium-3 counter, and new development on electronic concept for reprocessing nuclear waste plant (one electronic for multipurpose acquisition system). For nuclear safety and security for human and homeland will be introduce. First we will explain a new particular approach on operational dosimetric measurement and secondly, we will show new kind of organic scintillator material and associated electronics. Signal treatment with real time treatment is embedded, in order to make neutron gamma discrimination possible even in solid organic scintillator. Finally, the conclusion will point out future, with most trends in research and development on nuclear instrumentation for next years. (author) [fr

  7. Convention on the Physical Protection of Nuclear Material

    International Nuclear Information System (INIS)

    1980-01-01

    The convention on the Physical Protection of Nuclear Material is composed of the text of 23 articles, annex 1 showing the levels of physical protection and annex 2 which is the categorization list of nuclear material. The text consists of definitions (article 1), the scope of applications (2), liability of protecting nuclear material during international transport (3 and 4), duty of mutual cooperation (5 and 6), responsibility for criminal punishment (7 to 13), and final provisions (14 to 23). It is to be noted that the nuclear material for military purposes and domestic nuclear facilities are excluded in the connection. After the brief description of the course leading to the establishment of the convention, individual articles and annexes and the respective Japanese version, and the explanation based on the intergovernmental meeting discussion on the draft convention are described. (J.P.N.)

  8. Fissile and fertile nuclear material measurements using a new differential die-away self-interrogation technique

    International Nuclear Information System (INIS)

    Menlove, H.O.; Menlove, S.H.; Tobin, S.J.

    2009-01-01

    This paper presents a new technique for the measurement of fissile and fertile nuclear materials in spent fuel and plutonium-laden materials such as mixed oxide (MOX) fuel. The technique, called differential die-away self-interrogation, is similar to traditional differential die-away analysis, but it does not require a pulsed neutron generator or pulsed beam accelerator, and it can measure the fertile mass in addition to the fissile mass. The new method uses the spontaneous fission neutrons from 244 Cm in spent fuel and 240 Pu effective neutrons in MOX as the 'pulsed' neutron source, with an average of ∼2.7 neutrons per pulse. The time-correlated neutrons from the spontaneous fission and the subsequent induced fissions are analyzed as a function of time to determine the spontaneous fission rate, the induced fast-neutron fissions, and the induced thermal-neutron fissions. The fissile mass is determined from the induced thermal-neutron fissions that are produced by reflected thermal neutrons that originated from the spontaneous fission reaction. The sensitivity of the fissile mass measurement is enhanced by the use of two measurements, with and without a cadmium liner between the sample and a hydrogenous moderator that surrounds the sample. The fertile mass is determined from the multiplicity analysis of the neutrons detected soon after the initial triggering neutron is detected. The method obtains good sensitivity by the optimal design of two different neutron die-away regions: a short die-away for the neutron detector region and a longer die-away for the sample interrogation region.

  9. Physical protection of facilities and special nuclear materials in france

    International Nuclear Information System (INIS)

    Jeanpierre, G.

    1980-01-01

    Physical protection of nuclear facilities and special nuclear materials is subject in France to a national governmental regulation which provides for the basic principles to be taken into account and the minimal level of protection deemed necessary. But the responsibility of implementation is left to the facility management and the resulting decentralization allows for maximum efficiency. All safeguards measures comply with the commitments taken at the international level by the French government

  10. ANCRE alliance: Road-map for nuclear materials

    International Nuclear Information System (INIS)

    Touboul, F.; Carre, F.

    2013-01-01

    Created in 2009 by the Higher Education and Research ministry and by the Ecology ministry, ANCRE, the National Alliance for Energy Research Coordination aims at enhancing the efficiency of French research in the field of energy by promoting partnerships and synergies between public and private sectors (research organizations, universities and companies). ANCRE aims to propose a coordinated strategy for research and innovation projects. Beyond its four founding members, CEA, CNRS, IFPEN and CPU, ANCRE brings together all the French public research organizations concerned with energy issues, and has strong links with the industrial sector. Among the 10 programmatic groups of ANCRE, one is specifically dedicated to Nuclear Energies (fission and fusion). This group has proposed road-maps in five scientific fields, considered as strategic for R and D, in relation to industrial objectives and scientific bottlenecks: nuclear materials, nuclear chemistry, reactor physics, instrumentation and fusion. For twenty to thirty years, R and D on nuclear materials has evolved from the heavy metallurgy of the first generation of power reactors to the nano-materials science under extreme conditions for present and future needs. Nuclear systems are characterized by extreme operating conditions: high temperatures, mechanical stresses, radiations, corrosive environment, and long durations. In order to deal with these extreme conditions, it is necessary to have a sound knowledge of the materials, to the finest scale. R and D development was made possible by advances in materials science, in relation to more efficient observation means (now reaching the atom scale) and deeper control of the microstructure. Development of simulation methods at the atomic level (ab initio, classical molecular dynamics, kinetic Monte Carlo, etc.) have also allowed a better understanding of phenomena at their most fundamental level. Material performance issues, however, remain significant, as the performance

  11. National and international nuclear material monitoring

    International Nuclear Information System (INIS)

    Waddoups, I.G.

    1996-01-01

    The status of nuclear materials in both the U.S. and Former Soviet Union is changing based upon the execution of agreements relative to weapons materials production and weapon dismantlement. The result of these activities is that a considerably different emphasis is being placed on how nuclear materials are viewed and utilized. Even though much effort is being expended on the final disposition of these materials, the interim need for storage and security of the material is increasing. Both safety and security requirements exist to govern activities when these materials are placed in storage. These requirements are intended to provide confidence that the material is not being misused and that the storage operations are conducted safely. Both of these goals can be significantly enhanced if technological monitoring of the material is performed. This paper will briefly discuss the traditional manual methods of U.S. and international material monitoring and then present approaches and technology that are available to achieve the same goals under the evolving environment

  12. Protecting the source. Securing nuclear material and strong radiation sources. New threats of terrorism are prompting the need for swift action to better secure nuclear material and strong radiation sources. Are measures already in place enough? The Stanford-Salzburg initiative suggests not

    International Nuclear Information System (INIS)

    Steinhausler, F.; Bunn, G.

    2003-01-01

    At a time of growing concern over threats of terrorism, the security of nuclear and radioactive material is an urgent and serious issue. Working with a range of partners, the IAEA has put into place a multi-faceted Action Plan to help countries upgrade their capabilities. But more needs to be done to counter new types of threats. One particular area that needs to be strengthened is the physical protection of nuclear and radioactive material. The attacks of 11 September 2001 opened our eyes to i he urgent need to strengthen national physical protection (PP) practices for nuclear and other radioactive material. The principle that highly radioactive material will protect itself does not apply to the newest generation of terrorists. Existing PP systems were not designed to deal with the threat of suicidal terrorists commanding the numbers, skills, training, and resources available to those who carried out the attacks in the US. Moreover, because there are no mandatory international standards for domestic PP systems for nuclear or radioactive material, protection measures vary greatly from country to country. The IAEA recommended standards (Inference/225/Rev. 4) were not designed with the new terrorist threats in mind and national practices often fall short of even these recommendations. The result is inadequate protection against the new form of terrorism. Few argue the point that national physical protection practices for nuclear and other radioactive material need to be strengthened. This article summarizes a Stanford-Salzburg plan developed by experts from Stanford University's Center for International Security and Cooperation, (USA) and revised at the EU-Physical Protection NUMAT Conference in September 2002 in Salzburg, Austria. It includes six recommended elements to consider in addition to what the IAEA is now doing to improve PP practices around the world: Establish a global list of physical protection priorities; Create a multilateral security cooperation

  13. ASNC upgrade for nuclear material accountancy of ACPF

    Science.gov (United States)

    Seo, Hee; Ahn, Seong-Kyu; Lee, Chaehun; Oh, Jong-Myeong; Yoon, Seonkwang

    2018-02-01

    A safeguards neutron coincidence counter for nuclear material accountancy of the Advanced spent-fuel Conditioning Process Facility (ACPF), known as the ACP Safeguards Neutron Counter (ASNC), was upgraded to improve its remote-handling and maintenance capabilities. Based on the results of the previous design study, the neutron counter was completely rebuilt, and various detector parameters for neutron coincidence counting (i.e., high-voltage plateau, efficiency profile, dead time, die-away time, gate length, doubles gate fraction, and stability) were experimentally determined. The measurement data showed good agreement with the MCNP simulation results. To the best of the authors' knowledge, the ASNC is the only safeguards neutron coincidence counter in the world that is installed and operated in a hot-cell. The final goals to be achieved were (1) to evaluate the uncertainty level of the ASNC in nuclear material accountancy of the process materials of the oxide-reduction process for spent fuels and (2) to evaluate the applicability of the neutron coincidence counting technique within a strong radiation field (e.g., in a hot-cell environment).

  14. Responsible stewardship of nuclear materials

    International Nuclear Information System (INIS)

    Hannum, W.H.

    1994-01-01

    The ability to tap the massive energy potential of nuclear fission was first developed as a weapon to end a terrible world war. Nuclear fission is also a virtually inexhaustible energy resource, and is the only energy supply in certain areas in Russia, Kazakhstan and elsewhere. The potential link between civilian and military applications has been and continues to be a source of concern. With the end of the Cold War, this issue has taken a dramatic turn. The U.S. and Russia have agreed to reduce their nuclear weapons stockpiles by as much as two-thirds. This will make some 100 tonnes of separated plutonium and 500 tonnes of highly enriched uranium available, in a form that is obviously directly usable for weapons. The total world inventory of plutonium is now around 1000 tonnes and is increasing at 60-70 tonnes per year. There is even more highly enriched uranium. Fortunately the correct answer to what to do with excess weapons material is also the most attractive. It should be used and reused as fuel for fast reactors. Material in use (particularly nuclear material) is very easy to monitor and control, and is quite unattractive for diversion. Active management of fissile materials not only makes a major contribution to economic stability and well-being, but also simplifies accountability, inspection and other safeguards processes; provides a revenue stream to pay for the necessary safeguards; and, most importantly, limits the prospective world inventory of plutonium to only that which is used and useful

  15. General principles of the nuclear criticality safety for handling, processing and transportation fissile materials in the USSR

    International Nuclear Information System (INIS)

    Vnukov, V.S.; Rjazanov, B.G.; Sviridov, V.I.; Frolov, V.V.; Zubkov, Y.N.

    1991-01-01

    The paper describes the general principles of nuclear criticality safety for handling, processing, transportation and fissile materials storing. Measures to limit the consequences of critical accidents are discussed for the fuel processing plants and fissile materials storage. The system of scientific and technical measures on nuclear criticality safety as well as the system of control and state supervision based on the rules, limits and requirements are described. The criticality safety aspects for various stages of handling nuclear materials are considered. The paper gives descriptions of the methods and approaches for critical risk assessments for the processing facilities, plants and storages. (Author)

  16. Nuclear Security Systems and Measures for Major Public Events. Implementing Guide

    International Nuclear Information System (INIS)

    2012-01-01

    Terrorism remains a threat to international stability and security. High profile international and national major public events occur regularly, capturing great public interest and receiving intense media coverage. It is widely acknowledged that there is a substantial threat of a terrorist attack on major public events such as high profile political or economic summit meetings or major sporting contests. The threat of nuclear and radiological terrorism remains on the international security agenda. Nevertheless, to reduce this risk, the international community has made great progress in securing nuclear and other radioactive material that could otherwise be used in a terrorist act. This progress is contingent on the efforts of all States to adopt strong nuclear security systems and measures. There are large quantities of diverse radioactive material in existence, which are used in areas such as health, the environment, agriculture and industry. The hazards of this material vary according to composition and intensity. Additionally, the use of explosives in combination with this material can drastically enhance the impact of a criminal or terrorist act. If a criminal or terrorist group managed to detonate a so-called 'dirty' bomb in an urban area, the result could be mass panic, widespread radioactive contamination and major economic and social disruption. Major public events are seldom held in the same State or at the same location or even at the same venue. At the national level, the hosting of major public events with proper nuclear security arrangements can provide a foundation on which to build an enduring national framework for nuclear security; one that can exist long after the event. The organization of a major public event in which large numbers of people congregate presents complex security challenges for the State hosting such an event. Criminal or terrorist acts involving nuclear or other radioactive material at any major public event could result in

  17. Application of crime countermeasures for the protection of nuclear materials

    International Nuclear Information System (INIS)

    Bean, C.H.

    1975-01-01

    Federal regulations prepared by the Nuclear Regulatory Commission and published in the Federal Register require licensees to take appropriate action to protect the health and safety of the public from unauthorized use of special nuclear material (SNM), which includes plutonium, uranium-233, and highly enriched uranium. Crime countermeasures for compliance with these regulations are an important part of the guidance that is provided by the NRC's Office of Standards Development. The use of crime countermeasures and protective devices is intended to prevent the unauthorized diversion of material and to aid in the detection of diversion should it be attempted. Plant and equipment designs should incorporate both electronic and physical security measures for protection of SNM. This applies to facilities and equipment for reprocessing, fabrication, and transportation of SNM. The protection systems include physical barriers, access controls, intrusion detection devices, surveillance devices, central alarm stations, communications, and response capability. Acceptable security measures and devices applicable to protected areas, material access areas, vital areas, vital equipment, and transportation vehicles have been presented in Regulatory Guides. (U.S.)

  18. Legal aspects of transport of nuclear materials

    International Nuclear Information System (INIS)

    Jacobsson, Mans.

    The Paris Convention and the Brussels Supplementary Convention are briefly discussed and other conventions in the field of civil liability for nuclear damage are mentioned: the Vienna Convention, the Nuclear Ships Convention and the 1971 Convention relating to civil liability in the field of maritime carriage of nuclear material. Legislation on civil liability in the Nordic countries, which is based on the Paris Convention and the Supplementary Convention is discussed, notably the principle of channelling of liability and exceptions from that principle due to rules of liability in older transport conventions and certain problems due to the limited geographical scope of the Paris Convention and the Supplementary Convention. Insurance problems arising in connection with transport of nuclear materials are surveyed and an outline is given of the administrative provisions concerning transport (based on the IAEA transport regulations) which govern transport of radioactive materials by different means: road, rail, sea and air. Finally, the 1968 Treaty on the Non-Proliferation of Nuclear Weapons is discussed. (NEA) [fr

  19. Materials Science of High-Level Nuclear Waste Immobilization

    International Nuclear Information System (INIS)

    Weber, William J.; Navrotsky, Alexandra; Stefanovsky, S. V.; Vance, E. R.; Vernaz, Etienne Y.

    2009-01-01

    With the increasing demand for the development of more nuclear power comes the responsibility to address the technical challenges of immobilizing high-level nuclear wastes in stable solid forms for interim storage or disposition in geologic repositories. The immobilization of high-level nuclear wastes has been an active area of research and development for over 50 years. Borosilicate glasses and complex ceramic composites have been developed to meet many technical challenges and current needs, although regulatory issues, which vary widely from country to country, have yet to be resolved. Cooperative international programs to develop advanced proliferation-resistant nuclear technologies to close the nuclear fuel cycle and increase the efficiency of nuclear energy production might create new separation waste streams that could demand new concepts and materials for nuclear waste immobilization. This article reviews the current state-of-the-art understanding regarding the materials science of glasses and ceramics for the immobilization of high-level nuclear waste and excess nuclear materials and discusses approaches to address new waste streams

  20. Commissioning of calorimeter in radiochemical laboratory for non-destructive assay of special nuclear materials

    International Nuclear Information System (INIS)

    Patra, S.; Mhatre, A.M.; Agarwal, C.; Chaudhury, S.; Pujari, P.K.

    2017-01-01

    Accounting of special nuclear materials (SNM) in every stages of nuclear fuel cycle is a necessity where one needs the quantitative estimation of SNM in variety of samples like sealed containers or finished products without altering its physical and chemical form. Non-destructive assay (NDA) techniques are capable of assaying such samples by the way of measuring passive/active neutrons/gamma rays or by the measurement of decay heat. Radiochemistry Division has been actively involved in the development and deployment of various NDA methodologies for meeting the demand of nuclear material accounting as and when required. Recently a radiometric calorimeter, developed by Reactor Control Division, E and I Group, BARC, has been installed in Lab C-33, Radiochemistry Division

  1. U.S.-origin nuclear material removal program

    International Nuclear Information System (INIS)

    Messick, C.E.; Galan, J.J.

    2014-01-01

    The United States (U.S.) Department of Energy (DOE) Global Threat Reduction Initiative's (GTRI) U.S.-Origin Nuclear Material Removal program, also known as the Foreign Research Reactor Spent Nuclear Fuel Acceptance Program (FRR SNF AP), was established by the U.S. Department of Energy in May 1996. The program's mission provides a disposition pathway for certain U.S. origin spent nuclear fuel and other weapons-grade nuclear material. The program will continue until May 2016 with an additional three year window for fuel cooldown and transportation. This paper provides an update on recent program accomplishments, current program initiatives and future activities.

  2. An intelligence led approach to intercepting the illicit trafficking of nuclear and other radioactive material

    International Nuclear Information System (INIS)

    Kulinich, O.

    2001-01-01

    Recognizing the actuality and importance of nuclear material illicit trafficking problems, the Security Service of Ukraine pays great attention to the security and theft prevention of nuclear materials in Ukraine. For this purpose the state system, which includes organizational and legislative measures, has been established and is functioning. Within the frame of this system the detection and perception of illicit trafficking of nuclear materials and radioactive substances take an important place in the work of law enforcement authorities, including Security Service, in Ukraine. The Laws of Ukraine nuclear power utilization and radioactive safety, sanitary and epidemiological population control, the respective articles of the Criminal Code of Ukraine (art. 228-2, 228-3, 228-4, 228-5) and the statement of the Cabinet of Ministers of Ukraine no. 207 on 04.03.1997 which determines the interaction procedure between executive authorities in case of illicit trafficking of radiation source detection, are its legislative basis. The analysis of the situation shows that this problem became the most pressing after the USSR collapse in 1991 due to some objective and subjective causes. Some criminals and common staff of the enterprises and organizations which were responsible for the above mentioned materials as well as former military men were involved in illegal activity associated with illicit trafficking of nuclear materials and radioactive substances. Although after the USSR collapsed the Ukraine had the nuclear arsenal which was the third in the world, it did not become the source of nuclear weapons material proliferation. It shows the effectiveness of the measures undertaken by the government within the system of nuclear material physical protection provision. It is evident that nuclear weapon removal from the territory of Ukraine was performed without any case of its loss or theft. Therefore, currently in Ukraine there is only the necessary amount of nuclear material

  3. The convention on the physical protection of nuclear material

    International Nuclear Information System (INIS)

    1980-05-01

    This document contains the full text of a convention to facilitate the safe transfer of nuclear material, and to insure the physical protection of nuclear material in domestic use, storage, and transport. Two annexes are included, which establish categories of nuclear materials and levels of physical protection to be applied in international transport

  4. The use of modern databases in managing nuclear material inventories

    International Nuclear Information System (INIS)

    Behrens, R.G.

    1994-01-01

    The need for a useful nuclear materials database to assist in the management of nuclear materials within the Department of Energy (DOE) Weapons Complex is becoming significantly more important as the mission of the DOE Complex changes and both international safeguards and storage issues become drivers in determining how these materials are managed. A well designed nuclear material inventory database can provide the Nuclear Materials Manager with an essential cost effective tool for timely analysis and reporting of inventories. This paper discusses the use of databases as a management tool to meet increasing requirements for accurate and timely information on nuclear material inventories and related information. From the end user perspective, this paper discusses the rationale, philosophy, and technical requirements for an integrated database to meet the needs for a variety of users such as those working in the areas of Safeguards, Materials Control and Accountability (MC ampersand A), Nuclear Materials Management, Waste Management, materials processing, packaging and inspection, and interim/long term storage

  5. Ordinance concerning the filing of transport of nuclear fuel materials

    International Nuclear Information System (INIS)

    1987-01-01

    This Order provides provisions concerning nuclear fuel substances requiring notification (nuclear fuel substance, material contaminated with nuclear fuel substances, fissionable substances, etc.), procedure for notification (to prefectural public safety commission), certificate of transpot (issued via public safety commission), instructions (speed of vehicle for transporting nuclear fuel substances, parking of vehicle, place for loading and unloading of nuclear fuel substances, method for loading and unloading, report to police, measures for disaster prevention during transport, etc.), communication among members of public safety commission (for smooth transport), notification of alteration of data in transport certificate (application to be submitted to public safety commission), application of reissue of transport certificate, return of transport certificate, inspection concerning transport (to be performed by police), submission of report (to be submitted by refining facilities manager, processing facilities manager, nuclear reactor manager, master of foreign nuclear powered ship, reprocessing facilities manager, waste disposal facilities manager; concerning stolen or missing nuclear fuel substances, traffic accident, unusual leakage of nuclear fuel substances, etc.). (Nogami, K.)

  6. Materials aspects of nuclear waste isolation

    International Nuclear Information System (INIS)

    Bennett, J.W.

    1984-01-01

    This paper is intended to provide an overview of the nuclear waste repository performance requirements and the roles which we expect materials to play in meeting these requirements. The objective of the U.S. Dept. of Energy's (DOE) program is to provide for the safe, permanent isolation of high-level radioactive wastes from the public. The Nuclear Waste Policy Act of 1982 (the Act) provides the mandate to accomplish this objective by establishing a program timetable, a schedule of procedures to be followed, and program funding (1 mil/kwhr for all nuclear generated electricity). The centerpiece of this plan is the design and operation of a mined geologic repository system for the permanent isolation of radioactive wastes. A nuclear waste repository contains several thousand acres of tunnels and drifts into which the nuclear waste will be emplaced, and several hundred acres for the facilities on the surface in which the waste is received, handled, and prepared for movement underground. With the exception of the nuclear material-related facilities, a repository is similar to a standard mining operation. The difference comes in what a repository is supposed to do - to contain an isolate nuclear waste from man and the environment

  7. 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)

  8. Materials research in the Nuclear Research Centre Karlsruhe

    International Nuclear Information System (INIS)

    Kleykamp, H.

    1990-03-01

    This report gives a survey of the research work done at the Institute for Material and Solids Research at Karlsruhe. The following subjects are dealt with: Instrumental analysis; producing thin films; corrosion; failure mechanism and damage analysis; fuel elements, ceramic nuclear fuels and can and structure materials for fast breeder reactors; material problems and ceramic breeding materials for nuclear fusion plants; glass materials for the treatment of radioactive waste; super-conducting materials; amorphous metals, new high alloyed steels; ceramic high performance materials; hard materials; compound materials and polymers. (MM) [de

  9. Standard test method for nondestructive assay of special nuclear material holdup using Gamma-Ray spectroscopic methods

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2007-01-01

    1.1 This test method describes gamma-ray methods used to nondestructively measure the quantity of 235U, or 239Pu remaining as holdup in nuclear facilities. Holdup occurs in all facilities where nuclear material is processed, in process equipment, in exhaust ventilation systems and in building walls and floors. 1.2 This test method includes information useful for management, planning, selection of equipment, consideration of interferences, measurement program definition, and the utilization of resources (1, 2, 3, 4). 1.3 The measurement of nuclear material hold up in process equipment requires a scientific knowledge of radiation sources and detectors, transmission of radiation, calibration, facility operations and error analysis. It is subject to the constraints of the facility, management, budget, and schedule; plus health and safety requirements; as well as the laws of physics. The measurement process includes defining measurement uncertainties and is sensitive to the form and distribution of the material...

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

    International Nuclear Information System (INIS)

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

    2013-01-01

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

  11. Radiation damage in nuclear waste materials

    International Nuclear Information System (INIS)

    Jencic, I.

    2000-01-01

    Final disposal of high-level radioactive nuclear waste is usually envisioned in some sort of ceramic material. The physical and chemical properties of host materials for nuclear waste can be altered by internal radiation and consequently their structural integrity can be jeopardized. Assessment of long-term performance of these ceramic materials is therefore vital for a safe and successful disposal. This paper presents an overview of studies on several possible candidate materials for immobilization of fission products and actinides, such as spinel (MgAl 2 O 4 ), perovskite (CaTiO 3 ), zircon (ZrSiO 4 ), and pyrochlore (Gd 2 Ti 2 O 7 and Gd 2 Zr 2 O 7 ). The basic microscopic picture of radiation damage in ceramics consists of atomic displacements and ionization. In many cases these processes result in amorphization (metaminctization) of irradiated material. The evolution of microscopic structure during irradiation leads to various macroscopic radiation effects. The connection between microscopic and macroscopic picture is in most cases at least qualitatively known and studies of radiation induced microscopic changes are therefore an essential step in the design of a reliable nuclear waste host material. The relevance of these technologically important results on our general understanding of radiation damage processes and on current research efforts in Slovenia is also addressed. (author)

  12. Nuclear Space Power Systems Materials Requirements

    International Nuclear Information System (INIS)

    Buckman, R.W. Jr.

    2004-01-01

    High specific energy is required for space nuclear power systems. This generally means high operating temperatures and the only alloy class of materials available for construction of such systems are the refractory metals niobium, tantalum, molybdenum and tungsten. The refractory metals in the past have been the construction materials selected for nuclear space power systems. The objective of this paper will be to review the past history and requirements for space nuclear power systems from the early 1960's through the SP-100 program. Also presented will be the past and present status of refractory metal alloy technology and what will be needed to support the next advanced nuclear space power system. The next generation of advanced nuclear space power systems can benefit from the review of this past experience. Because of a decline in the refractory metal industry in the United States, ready availability of specific refractory metal alloys is limited

  13. Towards a new system of accounting of nuclear material

    International Nuclear Information System (INIS)

    Maceiras, Elena; Fernandez Moreno, Sonia; Castro, Laura B.; Saavedra, Analia D.; Mairal, M.L.; Valentino, Lucia I.; Vicens, Hugo E.; Llacer, Carlos D.

    1999-01-01

    The Nuclear Regulatory Authority (NRA) of Argentina has, among other functions, to ensure the fulfilment of national nuclear regulatory standards and all international safeguards commitments assumed by Argentina, particularly those related to the accounting and control of nuclear materials. To fulfil this responsibility, national inspections and audits of the operator's accounting and measurement systems are carried out, generating a great deal of data to be processed and evaluated. To manage this information in an efficient way, the RNA has implemented a control system composed by three database: SCMN, SIS and SOP, which interact amongst them. The objectives and functions of this integrated system and the achieved results to date are described in the present paper. (author)

  14. Nuclear reactor structural material forming less radioactive corrosion product

    International Nuclear Information System (INIS)

    Nakazawa, Hiroshi.

    1988-01-01

    Purpose: To provide nuclear reactor structural materials forming less radioactive corrosion products. Constitution: Ni-based alloys such as inconel alloy 718, 600 or inconel alloy 750 and 690 having excellent corrosion resistance and mechanical property even in coolants at high temperature and high pressure have generally been used as nuclear reactor structural materials. However, even such materials yield corrosion products being attacked by coolants circulating in the nuclear reactor, which produce by neutron irradiation radioactive corrosion products, that are deposited in primary circuit pipeways to constitute exposure sources. The present invention dissolves dissolves this problems by providing less activating nuclear reactor structural materials. That is, taking notice on the fact that Ni-58 contained generally by 68 % in Ni changes into Co-58 under irradiation of neutron thereby causing activation, the surface of nuclear reactor structural materials is applied with Ni plating by using Ni with a reduced content of Ni-58 isotopes. Accordingly, increase in the radiation level of the nuclear reactor structural materials can be inhibited. (K.M.)

  15. Better materials for nuclear energy

    International Nuclear Information System (INIS)

    Banerjee, S.

    2005-01-01

    The improved performance of present generation nuclear reactors and the realization of advanced reactor concepts, both, require development of better materials. Physical metallurgy /materials science principles which have been exploited in meeting the exacting requirements of nuclear systems comprising fuels, structural materials, moderators and coolants are outlined citing a few specific examples. While the incentive for improvement of traditional fuels (e.g., UO 2 fuel) is primarily for increasing the average core burn up, the development of advanced fuels (e.g., MOX, mixed carbide, nitride, silicide and dispersion fuels) are directed towards better utilization of fissile and fertile inventories through adaptation of innovative fuel cycles. As the burn up of UO 2 fuel reaches higher levels, a more detailed and quantitative understanding of the phenomena such as fission gas release, fuel restructuring - induced by radiation and thermal gradients and pellet-clad interaction is being achieved. Development of zirconium based alloys for both cladding and pressure tube applications is discussed with reference to their physical metallurgy, fabrication techniques, in-reactor degradation mechanisms, and in-service inspection. The issue of radiation embrittlement of reactor pressure vessels (RPVs) is covered drawing a comparison between the western and eastern specifications of RPV steels. The search for new materials which can stand higher rates of atomic displacement due to radiation has led to the development of swelling resistant austenitic and ferritic stainless steels for fast reactor applications as exemplified by the development of the D-9 steel for Indian fast breeder reactor. New challenges are thrown to material scientists for the development of materials suitable for high temperature reactors, which have a potential for providing primary heat for thermo chemical dissociation of water. Development of several ceramic materials, carbon based materials, dissimilar

  16. Large area nuclear particle detectors using ET materials

    International Nuclear Information System (INIS)

    1987-08-01

    The purpose of this SBIR Phase 1 feasibility effort was to demonstrate the usefulness of Quantex electron-trapping (ET) materials for spatial detection of nuclear particles over large areas. This demonstration entailed evaluating the prompt visible scintillation as nuclear particles impinged on films of ET materials, and subsequently detecting the nuclear particle impingement information pattern stored in the ET material, by means of the visible-wavelength luminescence produced by near-infrared interrogation. Readily useful levels of scintillation and luminescence outputs are demonstrated

  17. Escalation of terrorism? On the risk of attacks with chemical, biological, radiological and nuclear weapons or materials

    International Nuclear Information System (INIS)

    Nass, Jens

    2010-01-01

    The report on the risk of attacks with chemical, biological, radiological and nuclear weapons or materials covers the following topics: the variety of terrorism: ethnic-nationalistic, politically motivated, social revolutionary, political extremism, religious fanaticism, governmental terrorism; CBRN (chemical, biological, radiological, nuclear) weapons and materials: their availability and effectiveness in case of use; potential actor groups; prevention and counter measures, emergency and mitigating measures.

  18. Measuring strategy of Support Centre RIVM for nuclear emergencies

    International Nuclear Information System (INIS)

    Pruppers, M.J.M.; Smetsers, R.C.G.M.

    1994-11-01

    The accident at the Chernobyl nuclear power station in April 1986 and its consequences were reason for the Dutch government to evaluate and improve the facilities and the preparedness for nuclear emergency management in the Netherlands. The results of the evaluation have been elaborated in operational terms in the National Plan for Nuclear Emergency Planning and Response (EPR). During an accident with radioactive material the Technical Information Group (TIG) coordinates the measuring activities of the so-called Support Centres. According to the EPR, measuring activities of Support Centre RIVM are focussed on the collection and processing of data on emissions, concentrations, depositions and radiation doses from soil and air. This report describes the measuring strategy of RIVM for nuclear emergencies. The measuring strategy and the measuring plan, the latter deduced from the measuring strategy, concentrate on explicit answers to the following central questions: what has to be measured, by whom, where, when and how, and why? The demands of the TIG and the specification of tasks and operational facilities of Support Centre RIVM are considered as starting-points, limiting conditions and constraints for the measuring strategy. These items are converted to explicit choices for the measuring strategy and the default measuring plan. This report further includes a list of contacts of Support Centre RIVM with other (research) institutes, inside and outside the Netherlands, which may be relevant during a nuclear emergency. 3 figs., 2 tabs., 22 refs

  19. Nuclear Security Recommendations on Nuclear and Other Radioactive Material out of Regulatory Control: Recommendations

    International Nuclear Information System (INIS)

    2011-01-01

    This publication presents recommendations for the nuclear security of nuclear and other radioactive material that is out of regulatory control. It is based on national experiences and practices and guidance publications in the field of security as well as the nuclear security related international instruments. The recommendations include guidance for States with regard to the nuclear security of nuclear and other radioactive material that has been reported as being out of regulatory control as well as for material that is lost, missing or stolen but has not been reported as such, or has been otherwise discovered. In addition, these recommendations adhere to the detection and assessment of alarms and alerts and to a graded response to criminal or unauthorized acts with nuclear security implications

  20. Introduction of the Recycling program for Nuclear materials

    International Nuclear Information System (INIS)

    Park, Jae Beom; Shin, Byung Woo; Park, Jae Whan; Park, Soo Jin

    2009-01-01

    The LOF is the abbreviation of Location outside Facilities using in safeguards. IAEA want to control the location using the small nuclear material over the world. The depleted uranium used in Industrial field should be controlled by the Government according to the agreement between the IAEA and the ROK. From 2006, The ROK is managing the locations in the LOF. The detail article governing the locations is on the Location attachment agreed between two bodies. As of end of 2007, The LOF was consisting of 64 locations. Now, A number of Locations are increasing up to 75. The KINAC(Korea Institute of Nuclear Nonproliferation and Control) is controlling the data about the amount of nuclear material in LOF. The KINAC is trying to upgrade the efficiency and accuracy about the data. The KINAC will make a storage house at the underground of head office from 2009. The purpose of the storage system in KINAC is gathering the nuclear material, which is difficult to control by the industries, especially the nuclear material involved in LOF. The final goal for gathering the nuclear materials are recycling to new another machine. I would like to introduce the handling case of the Depleted uranium in their countries. On this paper, I will show 4 countries case briefly

  1. Radiation damage studies of nuclear structural materials

    International Nuclear Information System (INIS)

    Barat, P.

    2012-01-01

    Maximum utilization of fuel in nuclear reactors is one of the important aspects for operating them economically. The main hindrance to achieve this higher burnups of nuclear fuel for the nuclear reactors is the possibility of the failure of the metallic core components during their operation. Thus, the study of the cause of the possibility of failure of these metallic structural materials of nuclear reactors during full power operation due to radiation damage, suffered inside the reactor core, is an important field of studies bearing the basic to industrial scientific views.The variation of the microstructure of the metallic core components of the nuclear reactors due to radiation damage causes enormous variation in the structure and mechanical properties. A firm understanding of this variation of the mechanical properties with the variation of microstructure will serve as a guide for creating new, more radiation-tolerant materials. In our centre we have irradiated structural materials of Indian nuclear reactors by charged particles from accelerator to generate radiation damage and studied the some aspects of the variation of microstructure by X-ray diffraction studies. Results achieved in this regards, will be presented. (author)

  2. Characterization of semiconductor and frontier materials by nuclear microprobe technology

    International Nuclear Information System (INIS)

    Zhu Jieqing; Li Xiaolin; Yang Changyi; Lu Rongrong; Wang Jiqing; Guo Panlin

    2002-01-01

    The nuclear microprobe technology is used to characterize the properties of semiconductor and other frontier materials at the stages of their synthesis, modification, integration and application. On the basis of the beam current being used, the analytical nuclear microprobe techniques being used in this project can be divided into two categories: high beam current (PIXE, RBS, PEB) or low beam current (IBIC, STIM) techniques. The material properties measured are the thickness and composition of a composite surface on a SiC ceramic, the sputtering-induced surface segregation and depth profile change in a Ag-Cu binary alloy, the irradiation effects on the CCE of CVD diamond, the CCE profile at a polycrystalline CVD diamond film and a GaAs diode at different voltage biases and finally, the characterization of individual sample on an integrated material chip. (author)

  3. The application of a figure of merit for nuclear explosive utility as a metric for material attractiveness in a nuclear material theft scenario

    International Nuclear Information System (INIS)

    King, Wayne E.; Bradley, Keith; Jones, Edwin D.; Kramer, Kevin J.; Latkowski, Jeffery F.; Robel, Martin; Sleaford, Brad W.

    2010-01-01

    Effective integration of nonproliferation management into the design process is key to the broad deployment of advanced nuclear energy systems, and is an explicit goal of the Laser Inertial Fusion Energy (LIFE) project at Lawrence Livermore National Laboratory. The nuclear explosives utility of a nuclear material to a state (proliferator) or sub-state (terrorist) is a critical factor to be assessed and is one aspect of material attractiveness. In this work, we approached nuclear explosives utility through the calculation of a 'figure of merit' (FOM) that has recently been developed to capture the relative viability and difficulty of constructing nuclear explosives starting from various nuclear material forms and compositions. We discuss the integration of the figure of merit into an assessment of a nuclear material theft scenario and its use in the assessment. This paper demonstrates that material attractiveness is a multidimensional concept that embodies more than the FOM. It also seeks to propose that other attributes may be able to be quantified through analogous FOMs (e.g., transformation) and that, with quantification, aggregation may be possible using concepts from the risk community.

  4. U.S.-origin nuclear material removal program

    Energy Technology Data Exchange (ETDEWEB)

    Messick, C.E.; Galan, J.J. [U.S. Department of Energy, Washington, DC (United States). U.S.-Origin Nuclear Material Removal Program

    2014-12-15

    The United States (U.S.) Department of Energy (DOE) Global Threat Reduction Initiative's (GTRI) U.S.-Origin Nuclear Material Removal program, also known as the Foreign Research Reactor Spent Nuclear Fuel Acceptance Program (FRR SNF AP), was established by the U.S. Department of Energy in May 1996. The program's mission provides a disposition pathway for certain U.S. origin spent nuclear fuel and other weapons-grade nuclear material. The program will continue until May 2016 with an additional three year window for fuel cooldown and transportation. This paper provides an update on recent program accomplishments, current program initiatives and future activities.

  5. Research on technology of evaluating thermal property data of nuclear power materials

    International Nuclear Information System (INIS)

    Imai, Hidetaka; Baba, Tetsuya; Matsumoto, Tsuyoshi; Kishimoto, Isao; Taketoshi, Naoyuki; Arai, Teruo

    1997-01-01

    For the materials of first wall and diverter of nuclear fusion reactor, in order to withstand steady and unsteady high heat flux load, excellent thermal characteristics are required. It is strongly demanded to measure such thermal property values as heat conductivity, heat diffusivity, specific heat capacity, emissivity and so using small test pieces up to higher than 2000degC. As the materials of nuclear reactors are subjected to neutron irradiation, in order to secure the long term reliability of the materials, it is very important to establish the techniques for forecasting the change of the thermal property values due to irradiation effect. Also the establishment of the techniques for estimating the thermal property values of new materials like low radioactivation material is important. In National Research Laboratory of Metrology, the research on the advancement of the measuring technology for high temperature thermal properties has resulted in the considerably successful development of such technologies. In this research, the rapid measurement of thermal property values up to superhigh temperature with highest accuracy, the making of thermal property data set of high level, the analysis and evaluation of the correlation of material characters and thermal property values, and the development of the basic techniques for estimating the thermal property values of solid materials are aimed at and advanced. These are explained. (K.I.)

  6. The German system to prevent, detect and respond to illicit uses of nuclear materials and radioactive sources

    International Nuclear Information System (INIS)

    Fechner, J.B.

    2001-01-01

    The German system to prevent, detect and respond to illicit uses of nuclear materials and radioactive sources consists of a variety of different elements: International and national laws and regulations covering safeguards, physical protection, and import/export control; Licensing and regulatory supervision of all activities related to nuclear materials and radioactive sources, including import and export; Responsibility of the licensee to ensure compliance with licensing conditions; sanctions; Law enforcement by police, security and customs authorities; prosecution and penalties; Detection of illicitly trafficked radioactive materials through intelligence and technical means; analysis capabilities; Response arrangements for normal and for severe cases of illicit use of nuclear materials; Participation in international programmes and POC-systems. Safeguards measures have been implemented in Germany in accordance with the Non- Proliferation Treaty and with safeguards agreements based on INFCIRC/153. As Germany is a member of the European Union, the Euratom Treaty and the Euratom-Ordinance Nr. 3227/76 together with the Verification Agreement between the IAEA, the European Commission and the European Member States have led to safeguards measures jointly implemented by the IAEA and by Euratom. The relevant international law for the physical protection of nuclear material in force in Germany is the Convention on the Physical Protection of Nuclear Material. The recommendations on physical protection objectives and fundamentals and on physical protection measures specified in INFCIRC/225/Rev. 4 have been taken into account in various national regulations pertaining to the national design basis threat, the physical protection of LWR nuclear power plants, of interim spent fuel storage facilities, of facilities containing category III material, of nuclear material and radioactive waste transports by road or railway vehicles, aircraft or sea vessels; additional guidelines

  7. In-field analysis and assessment of nuclear material

    International Nuclear Information System (INIS)

    Morgado, R.E.; Myers, W.S.; Olivares, J.A.; Phillips, J.R.; York, R.L.

    1996-01-01

    Los Alamos National Laboratory has actively developed and implemented a number of instruments to monitor, detect, and analyze nuclear materials in the field. Many of these technologies, developed under existing US Department of Energy programs, can also be used to effectively interdict nuclear materials smuggled across or within national borders. In particular, two instruments are suitable for immediate implementation: the NAVI-2, a hand-held gamma-ray and neutron system for the detection and rapid identification of radioactive materials, and the portable mass spectrometer for the rapid analysis of minute quantities of radioactive materials. Both instruments provide not only critical information about the characteristics of the nuclear material for law-enforcement agencies and national authorities but also supply health and safety information for personnel handling the suspect materials

  8. Reliability of structural materials in nuclear industry

    International Nuclear Information System (INIS)

    Pinard Legry, G.

    1996-01-01

    The reliability of nuclear installations is a fundamental point for the exploitation of nuclear energy. It requires an extensive knowledge of the behaviour of materials in the operating conditions and during the expected service life of the installations. In nuclear power plants multiple risks of failure can exist and are expressed by corrosion and deformation phenomena or by modification in the mechanical characteristics of materials. The knowledge of the evolution with time of a given material requires to take into account the data relative to the material itself, to its environment and to the physical conditions of this environment. The study of materials aging needs a more precise knowledge of the kinetics of phenomena at any scale and of their interactions, and a micro- or macro-modeling of their behaviour during long periods of time. This paper gives an overview of the aging phenomena that occur in the structural materials involved in PWR and fast neutron reactors: thermal aging, generalized corrosion, corrosion under constraint, intergranular corrosion, crack growth under loading, wear, irradiation etc.. (J.S.)

  9. Nuclear data information system for nuclear materials

    International Nuclear Information System (INIS)

    Fujita, Mitsutane; Noda, Tetsuji; Utsumi, Misako

    1996-01-01

    The conceptual system for nuclear material design is considered and some trials on WWW server with functions of the easily accessible simulation of nuclear reactions are introduced. Moreover, as an example of the simulation on the system using nuclear data, transmutation calculation was made for candidate first wall materials such as 9Cr-2W steel, V-5Cr-5Ti and SiC in SUS316/Li 2 O/H 2 O(SUS), 9Cr-2W/Li 2 O/H 2 O(RAF), V alloy/Li/Be(V), and SiC/Li 2 ZrO 3 /He(SiC) blanket/shield systems based on ITER design model. Neutron spectrum varies with different blanket/shield compositions. The flux of low energy neutrons decreases in order of V< SiC< RAF< SUS blanket/shield systems. Fair amounts of W depletion in 9Cr-2W steel and the increase of Cr content in V-5Cr-5Ti were predicted in SUS or RAF systems. Concentration change in W and Cr is estimated to be suppressed if Li coolant is used in place of water. Helium and hydrogen production are not strongly affected by the different blanket/shield compositions. (author)

  10. Where do the Nuclear Materials Management functions fit in the Materials Control and Accountability (MC and A) plan?

    International Nuclear Information System (INIS)

    DeVer, E.A.

    1987-01-01

    Safeguards had its beginning in the early 1940s and has continued to grow through the stormy years in dealing with nuclear materials. MC and A Plans have been developed for each facility which includes requirements for containment, surveillance, internal controls, measurements, statistics, records and report systems, and inventory certification of its nuclear materials, in the context of how precisely the inventory is known at stated risk or confidence levels. The I and E Regulations, the newest document affecting the control system, are used for testing the current MC and A plan in place at each facility. Nuclear Materials Management activities also have reporting requirements that include: (1) Annual Forecast, (2) Materials Management Plan, (3) Quarterly Status Report, (4) Assessment Report, and (5) Scrap and Excess Material Management. Data used to generate reports for both functions come from the same data base and source documents at most facilities. The separation of sponsoring groups at the DOE for NM Accountability and NM Management can and does pose problems for contractors. In this paper, we will try to separate and identify these overlaps at the Facility and DOE level

  11. Statistical analysis of nuclear material weighing systems at the Oak Ridge - Y-12 plant

    International Nuclear Information System (INIS)

    Hammer, A.H.

    1980-04-01

    The variation in weight measurements on the electronic scales purchased for the Dynamic Special Nuclear Materials Control and Accountability System (DYMCAS) has been characterized and estimated to be more than is acceptable when using the current weighing methods. New weighing procedures have been developed which substantially reduce this variation and bring the weight errors within the Y-12 Plant Nuclear Materials Control and Accountability Department's desired +- 2-g accuracy

  12. Security of nuclear materials using fusion multi sensor wavelett

    International Nuclear Information System (INIS)

    Djoko Hari Nugroho

    2010-01-01

    Security of a nuclear material in an installation is determined by how far the installation is to assure that nuclear material remains at a predetermined location. This paper observed a preliminary design on nuclear material tracking system in the installation for decision making support based on multi sensor fusion that is reliable and accurate to ensure that the nuclear material remains inside the control area. Capability on decision making in the Management Information System is represented by an understanding of perception in the third level of abstraction. The second level will be achieved with the support of image analysis and organizing data. The first level of abstraction is constructed by merger between several CCD camera sensors distributed in a building in a data fusion representation. Data fusion is processed based on Wavelett approach. Simulation utilizing Matlab programming shows that Wavelett fuses multi information from sensors as well. Hope that when the nuclear material out of control regions which have been predetermined before, there will arise a warning alarm and a message in the Management Information System display. Thus the nuclear material movement time event can be obtained and tracked as well. (author)

  13. Regulation on control of nuclear materials of the 31 Oct 1986

    International Nuclear Information System (INIS)

    1986-01-01

    The new regulation on accounting for and control of nuclear materials was issued on 31 October 1986 and put into force on 1 February 1987. The following provisions are included: aim and scope, responsibility for nuclear material accounting and control, rights and obligations of the nuclear material control officer, licensing, facility's instructions for nuclear material control, accounting, records, reporting, unusual events, inspections, nuclear material transfers, exemptions and termination of IAEA safeguards, final provisions, and definitions of terms

  14. Moisture measurement in wood, wood-based materials and building materials - a literature review

    International Nuclear Information System (INIS)

    Kober, A.; Mehlhorn, L.; Plinke, B.

    1989-10-01

    Methods of moisture measurement in solid substances, especially on wood, wood-based materials and building materials were examined and evaluated according to the literature available. The question was which methods of examining the moisture distribution in building elements at climate loading offer the best accuracy and spatial resolution as well as which methods are the most appropriate at present and in future for the solution of measurement problems in the wood and wood-based industry. The most common methods are electric measurement methods which are utilizing either the moisture-depending conductivity or the dielectric constant or the reflectivity of the material for infrared radiation but they offer only a limited accuracy. The same is valid for the rarely used microwave methods or X-ray and NMR tomography. Simple electric methods will further on play an important role in the industrial process measuring technique. For the examination of building elements, methods using nuclear radiation still offer possibilities for a further development. (orig.) With 207 refs., 13 figs [de

  15. Survey of Technetium Analytical Production Methods Supporting Hanford Nuclear Materials Processing

    International Nuclear Information System (INIS)

    TROYER, G.L.

    1999-01-01

    This document provides a historical survey of analytical methods used for measuring 99 Tc in nuclear fuel reprocessing materials and wastes at Hanford. Method challenges including special sludge matrices tested are discussed. Special problems and recommendations are presented

  16. Noninvasive ultrasonic measurements of temperature distribution and heat fluxes in nuclear systems

    International Nuclear Information System (INIS)

    Jia, Yunlu; Skliar, Mikhail

    2015-01-01

    Measurements of temperature and heat fluxes through structural materials are important in many nuclear systems. One such example is dry storage casks (DSC) that are built to store highly radioactive materials, such as spent nuclear reactor fuel. The temperature inside casks must be maintained within allowable limits of the fuel assemblies and the DSC components because many degradation mechanisms are thermally controlled. In order to obtain direct, real-time measurements of temperature distribution without insertion of sensing elements into harsh environment of storage casks, we are developing noninvasive ultrasound (US) methods for measuring spatial distribution of temperature inside solid materials, such as concrete overpacks, steel casings, thimbles, and rods. The measured temperature distribution can then be used to obtain heat fluxes that provide calorimetric characterisation of the fuel decay, fuel distribution inside the cask, its integrity, and accounting of nuclear materials. The physical basis of the proposed approach is the temperature dependence of the speed of sound in solids. By measuring the time it takes an ultrasound signal to travel a known distance between a transducer and a receiver, the indication about the temperature distribution along the path of the ultrasound propagation may be obtained. However, when temperature along the path of US propagation is non-uniform, the overall time of flight of an ultrasound signal depends on the temperature distribution in a complex and unknown way. To overcome this difficulty, the central idea of our method is to create an US propagation path inside material of interest which incorporates partial ultrasound reflectors (back scatterers) at known locations and use the train of created multiple echoes to estimate the temperature distribution. In this paper, we discuss experimental validation of this approach, the achievable accuracy and spatial resolution of the measured temperature profile, and stress the

  17. Bar code usage in nuclear materials accountability

    International Nuclear Information System (INIS)

    Mee, W.T.

    1983-01-01

    The age old method of physically taking an inventory of materials by listing each item's identification number has lived beyond its usefulness. In this age of computerization, which offers the local grocery store a quick, sure, and easy means to inventory, it is time for nuclear materials facilities to automate accountability activities. The Oak Ridge Y-12 Plant began investigating the use of automated data collection devices in 1979. At that time, bar code and optical-character-recognition (OCR) systems were reviewed with the purpose of directly entering data into DYMCAS (Dynamic Special Nuclear Materials Control and Accountability System). Both of these systems appeared applicable; however, other automated devices already employed for production control made implementing the bar code and OCR seem improbable. However, the DYMCAS was placed on line for nuclear material accountability, a decision was made to consider the bar code for physical inventory listings. For the past several months a development program has been underway to use a bar code device to collect and input data to the DYMCAS on the uranium recovery operations. Programs have been completed and tested, and are being employed to ensure that data will be compatible and useful. Bar code implementation and expansion of its use for all nuclear material inventory activity in Y-12 is presented

  18. Aims and methods of nuclear materials management

    International Nuclear Information System (INIS)

    Leven, D.; Schier, H.

    1979-05-01

    Whilst international safeguarding of fissile materials against abuse has been the subject of extensive debate, little public attention has so far been devoted to the internal security of these materials. All countries using nuclear energy for peaceful purposes have laid down appropriate regulations. In the Federal Republic of Germany safeguards are required, for instance, by the Atomic Energy Act, and are therefore a prerequisite for licensing. The aims and methods of national nuclear materials management are contrasted with viewpoints on international safeguards

  19. Overview moderator material for nuclear reactor components

    International Nuclear Information System (INIS)

    Mairing Manutu Pongtuluran; Hendra Prihatnadi

    2009-01-01

    In order for a reactor design is considered acceptable absolute technical requirement is fulfilled because the most important part of a reactor design. Safety considerations emphasis on the handling of radioactive substances emitted during the operation of a reactor and radioactive waste handling. Moderator material is a layer that interacts directly with neutrons split the nuclear fuel that will lead to changes in physical properties, nuclear properties, mechanical properties and chemical properties. Reviews moderator of this time is of the types of moderator is often used to meet the requirements as nuclear material. (author)

  20. Illicit trafficking of nuclear material and other radioactive sources

    International Nuclear Information System (INIS)

    Yilmazer, A.; Yuecel, A.; Yavuz, U.

    2001-01-01

    As it is known, for the fact that the illicit trafficking and trading of nuclear materials are being increased over the past few years because of the huge demand of third world states. Nuclear materials like uranium, plutonium, and thorium are used in nuclear explosives that have very attractive features for crime groups, terrorist groups and, the states that are willing to have this power. Crime groups that make illegal trade of nuclear material are also trying to market strategic radioactive sources like red mercury and Osmium. This kind of illegal trade threats public safety, human health, environment also it brings significant threat on world peace and world public health. For these reasons, both states and international organizations should take a role in dealing with illicit trafficking. An important precondition for preventing this kind of incidents is the existence of a strengthened national system for control of all nuclear materials and other radioactive sources. Further, Governments are responsible for law enforcement within their borders for prevention of illegal trading and trafficking of nuclear materials and radiation sources

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

    International Nuclear Information System (INIS)

    Larrimore, J.A.

    1995-01-01

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

  2. Some ideas for next-generation controlled nuclear materials accountability techniques

    International Nuclear Information System (INIS)

    Brough, W.; Parrish, C.

    1994-08-01

    Current DOE regulations for Controlled Nuclear Materials (CNM) management have particular accounting problems that have become more evident as computer systems have been designed and programmed to automate the materials accounting functions. Some valuable detailed accounting information is lost with current accounting procedures and some aspects of the procedures are more complicated than need be. In February, 1988, the authors first recommended that the basic concepts of CNM accountability be reviewed, with particular emphasis on developing an Isotopic accountability system as opposed to the present Material-type accountability system. A parallel effort to review the materials measurement program would also be desirable

  3. Nuclear material control and accounting system evaluation in uranium conversion operations

    International Nuclear Information System (INIS)

    Moreira, Jose Pontes

    1994-01-01

    The Nuclear Material Control and Accounting Systems in uranium conversion operations are described. The conversion plant, uses ammonium diuranate (ADU), as starting material for the production of uranium hexafluoride. A combination of accountability and verification measurement is used to verify physical inventory quantities. Two types of inspection are used to minimize the measurements uncertainty of the Material Unaccounted For (MUF) : Attribute inspection and Variation inspection. The mass balance equation is the base of an evaluation of a Material Balance Area (MBA). Statistical inference is employed to facilitate rapid inventory taking and enhance material control of Safeguards. The calculation of one sampling plan for a MBA and the methodology of inspection evaluation are also described. We have two kinds of errors : no detection and false delation. (author)

  4. Nuclear Materials Diversion Safety and the Long-term Future of Nuclear Energy

    International Nuclear Information System (INIS)

    Knapp, V.

    2002-01-01

    Primarily due to irresponsible cold war politics of nuclear weapon countries nuclear proliferation situation is little short of getting out of control. In addition to five nominal nuclear weapon countries there are at present at least three more nuclear weapon countries and several countries with nuclear weapon potential. Non-proliferation treaty (NPT), signed in 1970, has been recognized by most non-nuclear weapon countries as unjust and ineffective. After the initial, deliberate, nuclear weapon developments of five nominal nuclear weapon countries, subsequent paths to nuclear weapons have been preceded by nominal peaceful use of nuclear energy. Uranium enrichment installations as well as reprocessing installations in non-nuclear weapon countries are the weakest spots of fuel cycle for diversion of nuclear materials either by governments or by illicit groups. An energy scenario, which would, by the end of century, replace the large part of fossil fuels use through extension of present nuclear practices, would mean very large increase in a number of such installations, with corresponding increase of the probability of diversion of nuclear materials. Such future is not acceptable from the point of view of proliferation safety. Recent events make it clear, that it cannot be accepted from the requirements of nuclear terrorism safety either. Nuclear community should put it clearly to their respective governments that the time has come to put general interest before the supposed national interest, by placing all enrichment and reprocessing installations under full international control. Such internationalization has a chance to be accepted by non-nuclear weapon countries, only in case should it apply to nuclear weapon countries as well, without exception. Recent terrorist acts, however horrible they were, are child,s play compared with possible acts of nuclear terrorism. Nuclear energy can be made proliferation safe and diversion of nuclear materials safe, and provide

  5. (Project 14-6770) An Investigation to Establish Multiphysical Property Dataset of Nuclear Materials Based on in-situ Observations and Measurements

    Energy Technology Data Exchange (ETDEWEB)

    Tomar, Vikas [Purdue Univ., West Lafayette, IN (United States); Haque, Aman [Pennsylvania State Univ., University Park, PA (United States). Dept of Physics; Hattar, Khalid [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-11-10

    In-core nuclear materials including fuel pins and cladding materials fail due to issues including corrosion, mechanical wear, and pellet cladding interaction. In most such scenario microstructure dependent and corrosioninduced chemistry dependent property changes significantly affect performance of cladding, pellet, and housing. Emphasis of this work was on replace conventional pellet-cladding material models with a new straingradient viscoplasticity model that is informed by transmission electron microscopy (TEM) based measurements and by nanomechanical Raman spectroscopy (NMRS) based measurements. The TEM measurements are quantitative in nature and therefore reveal stress-strain relations with simultaneous insights into mechanisms of deformation at nanoscale. The NMRS measurements reveal the similar information at mesoscale along with additional information on relating local microstructural stresses with applied stresses. The resulting information is used to fit constants in the strain gradient viscoplasticity model as well as to validate one. During TEM measurements, a micro-electro-mechanical system based setup was developed with mechanical actuation, sensing, heating, and electrical loading. Contrary to post-mortem analysis or qualitative visualization, this setup combines direct visualization of the mechanisms behind deformation with measurement of stress, strain, thermal and electrical properties. The unique research philosophy of visualizing the microstructure at high resolution while measuring the properties led to fundamental understanding in grain size and temperature effects on measured mechanical properties such as fracture toughness. A key contribution is the role of mechanical loading boundary conditions to deconvolute the insitu TEM based nanoscale and NMRS based mesoscale data to bulk behavior. First the literature based pellet cladding mechanical interaction model based on the work of Retel’s and Williamson’s in literature work to predict

  6. The application of a figure of merit for nuclear explosive utility as a metric for material attractiveness in a nuclear material theft scenario

    Energy Technology Data Exchange (ETDEWEB)

    King, Wayne E., E-mail: weking@llnl.go [Physical and Life Sciences Directorate, Lawrence Livermore National Laboratory, Livermore, CA 94551 (United States); Bradley, Keith [Global Security Directorate, Lawrence Livermore National Laboratory, Livermore, CA 94551 (United States); Jones, Edwin D. [Physical and Life Sciences Directorate, Lawrence Livermore National Laboratory, Livermore, CA 94551 (United States); Kramer, Kevin J.; Latkowski, Jeffery F. [Engineering Directorate, Lawrence Livermore National Laboratory, Livermore, CA 94551 (United States); Robel, Martin [Physical and Life Sciences Directorate, Lawrence Livermore National Laboratory, Livermore, CA 94551 (United States); Sleaford, Brad W. [Engineering Directorate, Lawrence Livermore National Laboratory, Livermore, CA 94551 (United States)

    2010-11-15

    Effective integration of nonproliferation management into the design process is key to the broad deployment of advanced nuclear energy systems, and is an explicit goal of the Laser Inertial Fusion Energy (LIFE) project at Lawrence Livermore National Laboratory. The nuclear explosives utility of a nuclear material to a state (proliferator) or sub-state (terrorist) is a critical factor to be assessed and is one aspect of material attractiveness. In this work, we approached nuclear explosives utility through the calculation of a 'figure of merit' (FOM) that has recently been developed to capture the relative viability and difficulty of constructing nuclear explosives starting from various nuclear material forms and compositions. We discuss the integration of the figure of merit into an assessment of a nuclear material theft scenario and its use in the assessment. This paper demonstrates that material attractiveness is a multidimensional concept that embodies more than the FOM. It also seeks to propose that other attributes may be able to be quantified through analogous FOMs (e.g., transformation) and that, with quantification, aggregation may be possible using concepts from the risk community.

  7. International nuclear data measurement activities. Newsletter No.3

    International Nuclear Information System (INIS)

    1998-12-01

    A survey is presented for various laboratories where nuclear data measurement facilities are applied to measure specific data. The laboratories are located in France (2 laboratories), in Germany (4 laboratories), in Japan (10 laboratories), in Russia (Institute of Physics and Power Engineering), in Sweden (Department of Neutron Research, Uppsala University), and in the USA (5 laboratories). Two international organizations are also included: Frank Laboratory of Neutron Physics, and Institute for Reference Materials and Measurements. (R.P.)

  8. Transportation of nuclear material in France: regulatory and technical aspects

    International Nuclear Information System (INIS)

    Flory, D.; Renard, C.

    1995-01-01

    Legislative and regulatory documentation define responsibilities in the field of security and physical protection for transportation of nuclear material. Any transportation activity has to conform to an advance authorization regime delivered by the Ministry of Industry. Responsibility for physical protection of nuclear material rests with the carrier under control of the public authority. Penalties reinforce this administrative regime. Operational responsibility for management and control of transport operations has been entrusted by the ministry to the operational transport unit (Echelon Operationnel des Transports - EOT) of IPSN (Institute for Nuclear Protection and Safety). To guarantee en efficient protection of transport operations, the various following means are provided for: -specialized transport means; - devices for real time tracking of road vehicles; - administrative authorization and declaration procedures; -intervention capacities in case of sabotage... This set of technical means and administrative measures is completed by the existence of a body of inspectors who may control every step of the operations. (authors). 3 tabs

  9. Control of nuclear materials and materials in Argentina

    International Nuclear Information System (INIS)

    Arbor G, A.; Fernandes M, S.

    1988-01-01

    A general view about the safeguards activities in Argentina is presented. The national system of accounting for and control of nuclear materials is described. The safeguards agreement signed by Argentina are presented. (E.G.) [pt

  10. Hungarian national nuclear material control and accounting system

    International Nuclear Information System (INIS)

    Lendvai, O.

    1985-01-01

    The Hungarian system for nuclear materials control and accounting is briefly described. Sections include a historical overview, a description of nuclear activities and an outline of the organizational structure of the materials management system. Subsequent sections discuss accounting, verification and international relations

  11. Upgrading nuclear material protection, control and accounting in Russia

    International Nuclear Information System (INIS)

    Caravelli, Jack; Behan, Chris; Fishbone, Les

    2001-01-01

    focus on implementation of the upgrades at the Russian nuclear sites, and on certain national or infrastructure areas: Regulatory Development; Training; Physical Inventory Taking and Material Balance; Computerized Material Accounting and Control; Bar Coding; Nondestructive Assay Measurements; Bulk (Weight and Volume) Measurements; Tamper-Indicating Devices; Nuclear Material Pedestrian Portal Monitors; Access Control; Building Hardening; Federal Information System. III. Results - To date, after more than six years of work, significant progress has been achieved in a variety of ways. For example: Security improvements are underway on some 750 metric tons of highly enriched uranium and plutonium at many sites under the supervision of Minatom, Gosatomnadzor, the Russian Navy, and other Russian entities. Among these are an ingenious concrete-block delay system for plutonium storage at the Mayak Production Association and an inventory strategy at the Institute of Physics and Power Engineering that, by fostering the consolidation of items, reduces the time required to inventory them. About 850 kg of HEU have been converted to low-enriched uranium in a project that is now active at two processing sites; More than 1000 Russian MPC and A staff have undergone training at the Russian Methodological and Training Center; and Hardening of more than 90 transport vehicles has enhanced transport security. We will illustrate this progress in the paper by describing the MPC and A upgrade work at specific Russian sites. IV. Discussion - During its existence, the MPC and A Program has confronted several problems. They include issues surrounding taxation, exports, travel, assurances, and business practice. Most have been overcome, but sometimes only after long and sustained effort. Positive results have been achieved because of the mutual desire of the United States and Russia to address the need for enhanced nuclear material protection, control and accounting at Russian nuclear sites. Yet

  12. Nuclear Materials Characterization in the Materials and Fuels Complex Analytical Hot Cells

    International Nuclear Information System (INIS)

    Rodriquez, Michael

    2009-01-01

    As energy prices skyrocket and interest in alternative, clean energy sources builds, interest in nuclear energy has increased. This increased interest in nuclear energy has been termed the 'Nuclear Renaissance'. The performance of nuclear fuels, fuels and reactor materials and waste products are becoming a more important issue as the potential for designing new nuclear reactors is more immediate. The Idaho National Laboratory (INL) Materials and Fuels Complex (MFC) Analytical Laboratory Hot Cells (ALHC) are rising to the challenge of characterizing new reactor materials, byproducts and performance. The ALHC is a facility located near Idaho Falls, Idaho at the INL Site. It was built in 1958 as part of the former Argonne National Laboratory West Complex to support the operation of the second Experimental Breeder Reactor (EBR-II). It is part of a larger analytical laboratory structure that includes wet chemistry, instrumentation and radiochemistry laboratories. The purpose of the ALHC is to perform analytical chemistry work on highly radioactive materials. The primary work in the ALHC has traditionally been dissolution of nuclear materials so that less radioactive subsamples (aliquots) could be transferred to other sections of the laboratory for analysis. Over the last 50 years though, the capabilities within the ALHC have also become independent of other laboratory sections in a number of ways. While dissolution, digestion and subdividing samples are still a vitally important role, the ALHC has stand alone capabilities in the area of immersion density, gamma scanning and combustion gas analysis. Recent use of the ALHC for immersion density shows that extremely fine and delicate operations can be performed with the master-slave manipulators by qualified operators. Twenty milligram samples were tested for immersion density to determine the expansion of uranium dioxide after irradiation in a nuclear reactor. The data collected confirmed modeling analysis with very tight

  13. Characterization of hydrogen, nitrogen, oxygen, carbon and sulfur in nuclear fuel (UO2) and cladding nuclear rod materials

    International Nuclear Information System (INIS)

    Crewe, Maria Teresa I.; Lopes, Paula Corain; Moura, Sergio C.; Sampaio, Jessica A.G.; Bustillos, Oscar V.

    2011-01-01

    The importance of Hydrogen, Nitrogen, Oxygen, Carbon and Sulfur gases analysis in nuclear fuels such as UO 2 , U 3 O 8 , U 3 Si 2 and in the fuel cladding such as Zircaloy, is a well known as a quality control in nuclear industry. In UO 2 pellets, the Hydrogen molecule fragilizes the metal lattice causing the material cracking. In Zircaloy material the H2 molecules cause the boiling of the cladding. Other gases like Nitrogen, Oxygen, Carbon and Sulfur affect in the lattice structure change. In this way these chemical compounds have to be measure within specify parameters, these measurement are part of the quality control of the nuclear industry. The analytical procedure has to be well established by a convention of the quality assurance. Therefore, the Oxygen, Carbon, Sulfur and Hydrogen are measured by infrared absorption (IR) and the nitrogen will be measured by thermal conductivity (TC). The gas/metal analyzer made by LECO Co. model TCHEN-600 is Hydrogen, Oxygen and Nitrogen analyzer in a variety of metals, refractory and other inorganic materials, using the principle of fusion by inert gas, infrared and thermo-coupled detector. The Carbon and Sulfur compounds are measure by LECO Co. model CS-400. A sample is first weighed and placed in a high purity graphite crucible and is casted on a stream of helium gas, enough to release the oxygen, nitrogen and hydrogen. During the fusion, the oxygen present in the sample combines with the carbon crucible to form carbon monoxide. Then, the nitrogen present in the sample is analyzed and released as molecular nitrogen and the hydrogen is released as gas. The hydrogen gas is measured by infrared absorption, and the sample gases pass through a trap of copper oxide which converts CO to CO 2 and hydrogen into water. The gases enter the cell where infrared water content is then converted making the measurement of total hydrogen present in the sample. The Hydrogen detection limits for the nuclear fuel is 1 μg/g for the Nitrogen

  14. Method and apparatus for measuring nuclear magnetic properties

    Science.gov (United States)

    Weitekamp, Daniel P.; Bielecki, Anthony; Zax, David B.; Zilm, Kurt W.; Pines, Alexander

    1987-01-01

    A method for studying the chemical and structural characteristics of materials is disclosed. The method includes placement of a sample material in a high strength polarizing magnetic field to order the sample nucleii. The condition used to order the sample is then removed abruptly and the ordering of the sample allowed to evolve for a time interval. At the end of the time interval, the ordering of the sample is measured by conventional nuclear magnetic resonance techniques.

  15. Nuclear safeguards: power tool for ensuring nuclear safety and security

    International Nuclear Information System (INIS)

    Ramakumar, K.L.

    2016-01-01

    The quantitative measurement of fissile nuclear materials through independent measurements is one of the cornerstones of the Nuclear Material Accounting and Control (NUMAC) edifice. The verification of the accountancy also represents one of the key elements of international nuclear materials Safeguards. The very basis of NUMAC is to ensure safeguarding nuclear material and to state with confidence, “no significant amount of nuclear material has been withdrawn from its intended civilian use.” Thus, materials accounting systems are designed to account for or keep track of the amounts and locations of sensitive nuclear materials by periodic measurements. The purpose of this activity is to detect missing items (gross defects). A variety of C/S techniques are used, primarily optical surveillance and sealing. These measures serve to back up nuclear material accountancy by providing means by which access to nuclear material can be monitored. Unattended monitoring is a special mode of application of NDA or C/S techniques, or a combination of these, that operates for extended periods of time. The complexity and diversity of facilities containing safeguarded nuclear material require a correspondingly diverse set of verification techniques and equipment. The equipment and techniques used in safeguards are briefly described in this talk

  16. Energy Frontier Research Center, Center for Materials Science of Nuclear Fuels

    Energy Technology Data Exchange (ETDEWEB)

    Todd R. Allen, Director

    2011-04-01

    The Office of Science, Basic Energy Sciences, has funded the INL as one of the Energy Frontier Research Centers in the area of material science of nuclear fuels. This document is the required annual report to the Office of Science that outlines the accomplishments for the period of May 2010 through April 2011. The aim of the Center for Material Science of Nuclear Fuels (CMSNF) is to establish the foundation for predictive understanding of the effects of irradiation-induced defects on thermal transport in oxide nuclear fuels. The science driver of the center’s investigation is to understand how complex defect and microstructures affect phonon mediated thermal transport in UO2, and achieve this understanding for the particular case of irradiation-induced defects and microstructures. The center’s research thus includes modeling and measurement of thermal transport in oxide fuels with different levels of impurities, lattice disorder and irradiation-induced microstructure, as well as theoretical and experimental investigation of the evolution of disorder, stoichiometry and microstructure in nuclear fuel under irradiation. With the premise that thermal transport in irradiated UO2 is a phonon-mediated energy transport process in a crystalline material with defects and microstructure, a step-by-step approach will be utilized to understand the effects of types of defects and microstructures on the collective phonon dynamics in irradiated UO2. Our efforts under the thermal transport thrust involved both measurement of diffusive phonon transport (an approach that integrates over the entire phonon spectrum) and spectroscopic measurements of phonon attenuation/lifetime and phonon dispersion. Our distinct experimental efforts dovetail with our modeling effort involving atomistic simulation of phonon transport and prediction of lattice thermal conductivity using the Boltzmann transport framework.

  17. Energy Frontier Research Center, Center for Materials Science of Nuclear Fuels

    International Nuclear Information System (INIS)

    Allen, Todd R.

    2011-01-01

    The Office of Science, Basic Energy Sciences, has funded the INL as one of the Energy Frontier Research Centers in the area of material science of nuclear fuels. This document is the required annual report to the Office of Science that outlines the accomplishments for the period of May 2010 through April 2011. The aim of the Center for Material Science of Nuclear Fuels (CMSNF) is to establish the foundation for predictive understanding of the effects of irradiation-induced defects on thermal transport in oxide nuclear fuels. The science driver of the center's investigation is to understand how complex defect and microstructures affect phonon mediated thermal transport in UO2, and achieve this understanding for the particular case of irradiation-induced defects and microstructures. The center's research thus includes modeling and measurement of thermal transport in oxide fuels with different levels of impurities, lattice disorder and irradiation-induced microstructure, as well as theoretical and experimental investigation of the evolution of disorder, stoichiometry and microstructure in nuclear fuel under irradiation. With the premise that thermal transport in irradiated UO2 is a phonon-mediated energy transport process in a crystalline material with defects and microstructure, a step-by-step approach will be utilized to understand the effects of types of defects and microstructures on the collective phonon dynamics in irradiated UO2. Our efforts under the thermal transport thrust involved both measurement of diffusive phonon transport (an approach that integrates over the entire phonon spectrum) and spectroscopic measurements of phonon attenuation/lifetime and phonon dispersion. Our distinct experimental efforts dovetail with our modeling effort involving atomistic simulation of phonon transport and prediction of lattice thermal conductivity using the Boltzmann transport framework.

  18. Procedures for the accounting and control of nuclear materials in large research centres, as related to the needs of international safeguards

    International Nuclear Information System (INIS)

    Kotte, U.; Bueker, H.; Stein, G.

    1976-07-01

    In signatory states of the Non-Proliferation Treaty nuclear material is subject to the supervision of the International Atomic Energy Agency. The IAEA safeguards concept intended for nuclear material has, so far, been predominantly applied to nuclear facilities of the nuclear fuel cycle. It is the aim of this report to consider the applicability of these control measures to a nuclear research centre. The report refers to the concrete example of the Juelich Nuclear Research Centre (KFA). The particular features of a nuclear research centre and the handling of nuclear material in the KFA are described. A review is given of the various licence areas and permitted handling quantities as well as of the inventories and flow of nuclear material. The concept of a control system for a nuclear research centre satisfying the operator's requirements, national requirement and international obligations at the same time is developed along these lines. The essential characteristic of the concept is a far-reaching clarity of the distribution of nuclear material items within the Nuclear Research Centre. The clarity desired will be achieved by means of an integrated accountancy system processing all necessary data with the aid of a central computer and remote terminals. The availability of information is based on differentiated material acountancy in conjunction with adequate measurement of nuclear material data. In the case of the KFA two groups are formed by research reactors and critical assemblies. Research institutes and central departments the permitted handling quantities of which do not exceed 5 eff.kg constitute a further group. Two further groups are formed for cases where the permitted handling quantities are above or below 1 eff.kg. The report shows the safeguards measures that can be applied in certain circumstances and conditions in a nuclear research centre

  19. Education and training in nuclear materials

    International Nuclear Information System (INIS)

    Falcon, S.; Marco, M.

    2014-01-01

    CIEMAT participates in the European project Matisse (Materials Innovations for a Safe and Sustainable nuclear in Europe) belonging to FP7, whose main objective is to promote the link between the respective national research programs through networking and integration of activities for innovation in materials for advanced nuclear systems, sharing among partners best practices and implementation of training tools and efficient communication. The draft four years, from 2013 to 2017, includes aspects such as the interaction between infrastructure, R and D programs and postgraduate education and training. (Author)

  20. Outline of a computerized nuclear material accounting system applicable to nuclear power reactors

    International Nuclear Information System (INIS)

    Handshuh, J.W.

    1975-01-01

    A computerized nuclear material accounting system is described which enables a utility to account for its material throughout the entire fuel cycle. From input of transactions, the system records and reports inventories and transactions by accounts which the user may establish for discrete locations, item control areas, further subdivisions, and material types. Account numbers are designed so that accounts and records are automatically sorted in the order desired. The system also generates the Material Status Reports for the Nuclear Regulatory Commission

  1. The national nuclear material tracking system. A Korea's countermeasure against nuclear terrorism

    Energy Technology Data Exchange (ETDEWEB)

    Moon, Joo Hyun [Dongguk Univ., Gyeongbuk (Korea, Republic of)

    2011-07-15

    Since nuclear terrorism has been identified as a real threat, the Korean government has earnestly developed elementary technologies and sub-systems for establishing an integrated defensive system against nuclear terrorism, which is based on the concept of defense-in-depth. This paper introduces the gist and implications of the studies that have been conducted in building the national nuclear material tracking system for preventing and intercepting the illicit trafficking and transporting of nuclear material in Korea. (orig.)

  2. US develops neutron to sniff out nuclear material

    CERN Document Server

    2002-01-01

    The USA has developed a tiny portable neutron device that can detect hidden nuclear materials. The device is undergoing trials in the Argonne National Laboratory to see if it could be used to stop smuggling and unauthorised use of nuclear weapons and materials (1/2 page).

  3. Variance and covariance calculations for nuclear materials accounting using ''MAVARIC''

    International Nuclear Information System (INIS)

    Nasseri, K.K.

    1987-07-01

    Determination of the detection sensitivity of a materials accounting system to the loss of special nuclear material (SNM) requires (1) obtaining a relation for the variance of the materials balance by propagation of the instrument errors for the measured quantities that appear in the materials balance equation and (2) substituting measured values and their error standard deviations into this relation and calculating the variance of the materials balance. MAVARIC (Materials Accounting VARIance Calculations) is a custom spreadsheet, designed using the second release of Lotus 1-2-3, that significantly reduces the effort required to make the necessary variance (and covariance) calculations needed to determine the detection sensitivity of a materials accounting system. Predefined macros within the spreadsheet allow the user to carry out long, tedious procedures with only a few keystrokes. MAVARIC requires that the user enter the following data into one of four data tables, depending on the type of the term in the materials balance equation; the SNM concentration, the bulk mass (or solution volume), the measurement error standard deviations, and the number of measurements made during an accounting period. The user can also specify if there are correlations between transfer terms. Based on these data entries, MAVARIC can calculate the variance of the materials balance and the square root of this variance, from which the detection sensitivity of the accounting system can be determined

  4. Variance and covariance calculations for nuclear materials accounting using 'MAVARIC'

    International Nuclear Information System (INIS)

    Nasseri, K.K.

    1987-01-01

    Determination of the detection sensitivity of a materials accounting system to the loss of special nuclear material (SNM) requires (1) obtaining a relation for the variance of the materials balance by propagation of the instrument errors for the measured quantities that appear in the materials balance equation and (2) substituting measured values and their error standard deviations into this relation and calculating the variance of the materials balance. MAVARIC (Materials Accounting VARIance Calculations) is a custom spreadsheet, designed using the second release of Lotus 1-2-3, that significantly reduces the effort required to make the necessary variance (and covariance) calculations needed to determine the detection sensitivity of a materials accounting system. Predefined macros within the spreadsheet allow the user to carry out long, tedious procedures with only a few keystrokes. MAVARIC requires that the user enter the following data into one of four data tables, depending on the type of the term in the materials balance equation; the SNM concentration, the bulk mass (or solution volume), the measurement error standard deviations, and the number of measurements made during an accounting period. The user can also specify if there are correlations between transfer terms. Based on these data entries, MAVARIC can calculate the variance of the materials balance and the square root of this variance, from which the detection sensitivity of the accounting system can be determined

  5. The fluence research of filter material for fast neutron fluence measurement

    International Nuclear Information System (INIS)

    Tang Xiding

    2010-01-01

    When the fast neutron fluence is measured by radioactivation techniques in the nuclear reactor the fast neutron is also filtered a little by the thermal neutron filter material, and if the filter material thickness increase the filtered fast neutron increases therewith. For fast neutron fluenc measurement, there are only cadmium, boron and gadolinium three elements filtering fluence can be calculated ordinarily. In order to calculate the filtered fast neutron fluence of the all elements in the filter material, the many total cross sections of nuclides had checked out from nuclear cross section data library, converted them into the same energy group structure, then element's total cross section, compound's total cross section and multilayer filters' total cross section had calculated from these total cross sections with same energy group structure, a new cross section data library can be obtained lastly through merging these cross sections into the old cross section data library used for neutron fluence measurement. The calculation analysis indicates that the results of the unit 2 surveillance capsule U of DAYA Bay NPP and the unit 1 surveillance capsule A of the Second Nuclear Power Plant of Qinshan by considering the all elements subtracting iron are smaller about 1.5% and 2.6% respectively than the ones only to consider cadmium, boron. The old measured results accord with the new values under the measurement uncertainty, are reliable. The new results are more accuracy. (authors)

  6. Computerized nuclear material database management system for power reactors

    International Nuclear Information System (INIS)

    Cheng Binghao; Zhu Rongbao; Liu Daming; Cao Bin; Liu Ling; Tan Yajun; Jiang Jincai

    1994-01-01

    The software packages for nuclear material database management for power reactors are described. The database structure, data flow and model for management of the database are analysed. Also mentioned are the main functions and characterizations of the software packages, which are successfully installed and used at both the Daya Bay Nuclear Power Plant and the Qinshan Nuclear Power Plant for the purposed of handling nuclear material database automatically

  7. Software development for managing nuclear material database; Desenvolvimento de um programa computacional para gerenciamento de banco de dados de material nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Tondin, Julio Benedito Marin

    2011-07-01

    In nuclear facilities, the nuclear material control is one of the most important activities. The Brazilian National Commission of Nuclear Energy (CNEN) and the International Atomic Energy Agency (IAEA), when inspecting routinely, regards the data provided as a major safety factor. Having a control system of nuclear material that allows the amount and location of the various items to be inspected, at any time, is a key factor today. The objective of this work was to enhance the existing system using a more friendly platform of development, through the VisualBasic programming language (Microsoft Corporation), to facilitate the operation team of the reactor IEA-R1 Reactor tasks, providing data that enable a better and prompter control of the IEA-R1 nuclear material. These data have allowed the development of papers presented at national and international conferences and the development of master's dissertations and doctorate theses. The software object of this study was designed to meet the requirements of the CNEN and the IAEA safeguard rules, but its functions may be expanded in accordance with future needs. The program developed can be used in other reactors to be built in the country, since it is very practical and allows an effective control of the nuclear material in the facilities. (author)

  8. Nondestructive assay of special nuclear material for uranium fuel-fabrication facilities

    International Nuclear Information System (INIS)

    Smith, H.A. Jr.; Schillebeeckx, P.

    1997-01-01

    A high-quality materials accounting system and effective international inspections in uranium fuel-fabrication facilities depend heavily upon accurate nondestructive assay measurements of the facility's nuclear materials. While item accounting can monitor a large portion of the facility inventory (fuel rods, assemblies, storage items), the contents of all such items and mass values for all bulk materials must be based on quantitative measurements. Weight measurements, combined with destructive analysis of process samples, can provide highly accurate quantitative information on well-characterized and uniform product materials. However, to cover the full range of process materials and to provide timely accountancy data on hard-to-measure items and rapid verification of previous measurements, radiation-based nondestructive assay (NDA) techniques play an important role. NDA for uranium fuel fabrication facilities relies on passive gamma spectroscopy for enrichment and U isotope mass values of medium-to-low-density samples and holdup deposits; it relies on active neutron techniques for U-235 mass values of high-density and heterogeneous samples. This paper will describe the basic radiation-based nondestructive assay techniques used to perform these measurements. The authors will also discuss the NDA measurement applications for international inspections of European fuel-fabrication facilities

  9. Selection of materials in nuclear fuel: present and future

    International Nuclear Information System (INIS)

    Munoz-Reja, C.; Fuentes, L.; Garcia de la Infanta, J. M.; Munoz Sicilia, A.

    2013-01-01

    One of the main aspects of the nuclear fuel is the selection of materials for the components. The operating conditions of the fuel elements impose a major challenge to materials: high temperature, corrosive aqueous environment, high mechanical properties, long periods of time under these extreme conditions and what is the differentiating factor; the effect of irradiation. The materials are selected to fulfill these severe requirements and also to be able to control and to predict its behavior in the working conditions. Their development, in terms of composition and processing, is based on the continuous follow-up of the operation behavior. Many of these materials are specific of the nuclear industry, such as the uranium dioxide and the zirconium alloys. This article presents the selection and development of the nuclear fuel materials as a function of the services requirements. It also includes a view of the new nuclear fuels materials that are being raised after Fukushima accident. (Author)

  10. Nuclear and hazardous material perspective

    International Nuclear Information System (INIS)

    Sandquist, Gary M.; Kunze, Jay F.; Rogers, Vern C.

    2007-01-01

    The reemerging nuclear enterprise in the 21. century empowering the power industry and nuclear technology is still viewed with fear and concern by many of the public and many political leaders. Nuclear phobia is also exhibited by many nuclear professionals. The fears and concerns of these groups are complex and varied, but focus primarily on (1) management and disposal of radioactive waste [especially spent nuclear fuel and low level radioactive waste], (2) radiation exposures at any level, and (3) the threat nuclear terrorism. The root cause of all these concerns is the exaggerated risk perceived to human health from radiation exposure. These risks from radiation exposure are compounded by the universal threat of nuclear weapons and the disastrous consequences if these weapons or materials become available to terrorists or rogue nations. This paper addresses the bases and rationality for these fears and considers methods and options for mitigating these fears. Scientific evidence and actual data are provided. Radiation risks are compared to similar risks from common chemicals and familiar human activities that are routinely accepted. (authors)

  11. 10 CFR 70.11 - Persons using special nuclear material under certain Department of Energy and Nuclear Regulatory...

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Persons using special nuclear material under certain Department of Energy and Nuclear Regulatory Commission contracts. 70.11 Section 70.11 Energy NUCLEAR... using special nuclear material under certain Department of Energy and Nuclear Regulatory Commission...

  12. The Application of materials attractiveness in a graded approach to nuclear materials security

    International Nuclear Information System (INIS)

    Ebbinghaus, B.; Bathke, C.; Dalton, D.; Murphy, J.

    2013-01-01

    The threat from terrorist groups has recently received greater attention. In this paper, material quantity and material attractiveness are addressed through the lens of a minimum security strategy needed to prevent the construction of a nuclear explosive device (NED) by an adversary. Nuclear materials are placed into specific security categories (3 or 4 categories) , which define a number of security requirements to protect the material. Materials attractiveness can be divided into four attractiveness levels, High, Medium, Low, and Very Low that correspond to the utility of the material to the adversary and to a minimum security strategy that is necessary to adequately protect the nuclear material. We propose a graded approach to materials attractiveness that recognizes for instance substantial differences in attractiveness between pure reactor-grade Pu oxide (High attractiveness) and fresh MOX fuel (Low attractiveness). In either case, an adversary's acquisition of a Category I quantity of plutonium would be a major incident, but the acquisition of Pu oxide by the adversary would be substantially worse than the acquisition of fresh MOX fuel because of the substantial differences in the time and complexity required of the adversary to process the material and fashion it into a NED

  13. Risk perception and communication strategies for the disposal of nuclear material

    International Nuclear Information System (INIS)

    Taghizadegan, R.; Tschurlovits, M.

    2005-01-01

    The public perception of the risk due to disposal of nuclear material depends less on risk as a quantifiable measure, but rather on particular patterns of societal communication. Only an understanding of these patterns and the underlying motives permits effective risk communication in the form of a risk dialogue. Risk becomes a social code word and risk communication a social process, which is determined by ''rituals'' like stigmas and taboos on one hand, and on the other hand competing world views. The latter are analyzed by means of ''Cultural Theory'' and thus diverging perceptions of risks are explained. Finally, some communication strategies on the risks and uncertainties of the disposal of nuclear material are presented. (orig.)

  14. Special nuclear material simulation device

    Science.gov (United States)

    Leckey, John H.; DeMint, Amy; Gooch, Jack; Hawk, Todd; Pickett, Chris A.; Blessinger, Chris; York, Robbie L.

    2014-08-12

    An apparatus for simulating special nuclear material is provided. The apparatus typically contains a small quantity of special nuclear material (SNM) in a configuration that simulates a much larger quantity of SNM. Generally the apparatus includes a spherical shell that is formed from an alloy containing a small quantity of highly enriched uranium. Also typically provided is a core of depleted uranium. A spacer, typically aluminum, may be used to separate the depleted uranium from the shell of uranium alloy. A cladding, typically made of titanium, is provided to seal the source. Methods are provided to simulate SNM for testing radiation monitoring portals. Typically the methods use at least one primary SNM spectral line and exclude at least one secondary SNM spectral line.

  15. Characterization and testing of materials for nuclear reactors. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2007-03-01

    Nuclear techniques in general and neutrons based methods in particular have played and will continue to play an important role in research in materials science and technology. Today the world is looking at nuclear fission and nuclear fusion as the main sources of energy supply for the future. Research reactors have played a key role in the development of nuclear technology. A materials development programme will thus play a major role in the design and development of new nuclear power plants, for the extension of the life of operating reactors as well as for fusion reactors. Against this background, the IAEA had organized a Technical Meeting on Development, Characterization and Testing of Materials - With Special Reference to the Energy Sector under the activity on specific applications of research reactors. The meeting was held in Vienna, May 29- June 2, 2006. There was also participation by experts in techniques, complementary to neutrons. The participants for the technical meeting were experts in the utilization of nuclear techniques namely the high flux and medium flux research reactors, fusion research and positron annihilation. They presented the design, development and utilization of the facilities at their respective centres for materials characterization with main focus on materials for nuclear energy, both fission and fusion. In core irradiation of materials, development of instrument for residual stress measurement in large and / or irradiated specimen, neutron radiography for inspection of irradiated fuel, work on oxide dispersion strengthened (ODS) steels and SiC composites, relevant to future power systems were cited as application of nuclear techniques in fission reactors. The use of neutron scattering for helium bubbles in steel, application of positron annihilation to study helium bubbles in Cu, Ti-stabilized stainless steel and voidswelling studies etc. show that these techniques have an important role in the development of materials for energy

  16. Order for execution of the law concerning regulations of nuclear source materials, nuclear fuel materials and reactors

    International Nuclear Information System (INIS)

    1987-01-01

    Chapeter 1 specifies regulations concerning business management for refining and processing, which cover application for designation of refining operation, application for permission for processing operation, and approval of personnel responsible for handling nuclear fuel. Chapter 2 specifies regulations concerning construction and operation of nuclear reactors, which cover application for construction of nuclear reactors, reactors in a research and development stage, application for permission concerning nuclear reactors mounted on foreign nuclear powered ships, application for permission for alteration concerning construction of nuclear reactors, application for permission for alteration concerning nuclear reactors mounted on foreign nuclear powered ships, nuclear reactor facilities to be subjected to regular inspection, nuclear reactor for which submission of operation plan is not required, and application for permission for transfer of nuclear reactor. Chapter 2 also specifies regulations concerning business management for reprocessing and waste disposal. Chapter 3 stipulates regulations concerning use of nuclear fuel substances, nuclear material substances and other substances covered by international regulations, which include rules for application for permission for use of nuclear fuel substances, etc. Supplementary provisions are provided in Chapter 4. (Nogami, K.)

  17. Atomistic Simulations of Small-scale Materials Tests of Nuclear Materials

    International Nuclear Information System (INIS)

    Shin, Chan Sun; Jin, Hyung Ha; Kwon, Jun Hyun

    2012-01-01

    Degradation of materials properties under neutron irradiation is one of the key issues affecting the lifetime of nuclear reactors. Evaluating the property changes of materials due to irradiations and understanding the role of microstructural changes on mechanical properties are required for ensuring reliable and safe operation of a nuclear reactor. However, high dose of neuron irradiation capabilities are rather limited and it is difficult to discriminate various factors affecting the property changes of materials. Ion beam irradiation can be used to investigate radiation damage to materials in a controlled way, but has the main limitation of small penetration depth in the length scale of micro meters. Over the past decade, the interest in the investigations of size-dependent mechanical properties has promoted the development of various small-scale materials tests, e.g. nanoindentation and micro/nano-pillar compression tests. Small-scale materials tests can address the issue of the limitation of small penetration depth of ion irradiation. In this paper, we present small-scale materials tests (experiments and simulation) which are applied to study the size and irradiation effects on mechanical properties. We have performed molecular dynamics simulations of nanoindentation and nanopillar compression tests. These atomistic simulations are expected to significantly contribute to the investigation of the fundamental deformation mechanism of small scale irradiated materials

  18. Materials for Nuclear Plants From Safe Design to Residual Life Assessments

    CERN Document Server

    Hoffelner, Wolfgang

    2013-01-01

    The clamor for non-carbon dioxide emitting energy production has directly  impacted on the development of nuclear energy. As new nuclear plants are built, plans and designs are continually being developed to manage the range of challenging requirement and problems that nuclear plants face especially when managing the greatly increased operating temperatures, irradiation doses and extended design life spans. Materials for Nuclear Plants: From Safe Design to Residual Life Assessments  provides a comprehensive treatment of the structural materials for nuclear power plants with emphasis on advanced design concepts.   Materials for Nuclear Plants: From Safe Design to Residual Life Assessments approaches structural materials with a systemic approach. Important components and materials currently in use as well as those which can be considered in future designs are detailed, whilst the damage mechanisms responsible for plant ageing are discussed and explained. Methodologies for materials characterization, material...

  19. Analytical chemistry of nuclear materials

    International Nuclear Information System (INIS)

    1963-01-01

    The last two decades have witnessed an enormous development in chemical analysis. The rapid progress of nuclear energy, of solid-state physics and of other fields of modern industry has extended the concept of purity to limits previously unthought of, and to reach the new dimensions of these extreme demands, entirely new techniques have been invented and applied and old ones have been refined. Recognizing these facts, the International Atomic Energy Agency convened a Panel on Analytical Chemistry of Nuclear Materials to discuss the general problems facing the analytical chemist engaged in nuclear energy development, particularly in newly developing centre and countries, to analyse the represent situation and to advise as to the directions in which research and development appear to be most necessary. The Panel also discussed the analytical programme of the Agency's laboratory at Seibersdorf, where the Agency has already started a programme of international comparison of analytical methods which may lead to the establishment of international standards for many materials of interest. Refs and tabs

  20. Nuclear Materials Management U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO)

    International Nuclear Information System (INIS)

    Jesse Schreiber

    2008-01-01

    In light of the changing Defense Complex mission, the high cost to storing and protecting nuclear materials, and in consideration of scarcity of resources, it is imperative that the U.S. Department of Energy (DOE) owned nuclear materials are managed effectively. The U.S. Department of Energy, National Nuclear Security Administration (NNSA) Strategic Action Plan outlines the strategy for continuing to meet America's nuclear security goals, meeting the overall mission challenges of DOE and NNSA as well as giving focus to local missions. The mission of the NNSA/NSO Nuclear Materials Management (NMM) Program is to ensure that nuclear material inventories are accurately assessed and reported, future material needs are adequately planned, and that existing Nevada Test Site (NTS) inventories are efficiently utilized, staged, or dispositioned. The NNSA/NSO understands that the NTS has unique characteristics to serve and benefit the nation with innovative solutions to the complex problems involving Special Nuclear Materials, hazardous materials, and multi-agency, integrated operations. The NNSA/NSO is defining infrastructure requirements for known future missions, developing footprint consolidation strategic action plans, and continuing in the path of facility modernization and improvements. The NNSA/NSO is striving for the NTS to be acknowledged as an ideal location towards mission expansion and growth. The NTS has the capability of providing isolated, large scale construction and development locations for nuclear power or alternate energy source facilities, expanded nuclear material storage sites, and for new development in 'green' technology

  1. Evaluation and development of advanced nuclear materials: IAEA activities

    International Nuclear Information System (INIS)

    Inozemtsev, V.; Basak, U.; Killeen, J.; Dyck, G.; Zeman, A.; )

    2011-01-01

    Economical, environmental and non-proliferation issues associated with sustainable development of nuclear power bring about a need for optimization of fuel cycles and implementation of advanced nuclear systems. While a number of physical and design concepts are available for innovative reactors, the absence of reliable materials able to sustain new challenging irradiation conditions represents the real bottle-neck for practical implementation of these promising ideas. Materials performance and integrity are key issues for the safety and competitiveness of future nuclear installations being developed for sustainable nuclear energy production incorporating fuel recycling and waste transmutation systems. These systems will feature high thermal operational efficiency, improved utilization of resources (both fissile and fertile materials) and reduced production of nuclear waste. They will require development, qualification and deployment of new and advanced fuel and structural materials with improved mechanical and chemical properties combined with high radiation and corrosion resistance. The extensive, diverse, and expensive efforts toward the development of these materials can be more effectively organized within international collaborative programmes with wide participation of research, design and engineering communities. IAEA carries out a number of international projects supporting interested Member States with the use of available IAEA program implementation tools (Coordinated Research Projects, Technical Meetings, Expert Reviews, etc). The presentation summarizes the activities targeting material developments for advanced nuclear systems, with particular emphasis on fast reactors, which are the focal topics of IAEA Coordinated Research Projects 'Accelerator Simulation and Theoretical Modelling of Radiation Effects' (on-going), 'Benchmarking of Structural Materials Pre-Selected for Advanced Nuclear Reactors', 'Examination of advanced fast reactor fuel and core

  2. Nuclear material control in the United States

    International Nuclear Information System (INIS)

    Jaeger, C.; Waddoups, I.

    1995-01-01

    The Department of Energy has defined a safeguards system to be an integrated system of physical protection, material accounting and material control subsystems designed to deter, prevent, detect, and respond to unauthorized possession, use, or sabotage of SNM. In practice, safeguards involve the development and application of techniques and procedures dealing with the establishment and continued maintenance of a system of activities. The system must also include administrative controls and surveillance to assure that the procedures and techniques of the system are effective and are being carried out. The control of nuclear material is critical to the safeguarding of nuclear materials within the United States. The U.S. Department of Energy includes as part of material control four functional performance areas. They include access controls, material surveillance, material containment and detection/assessment. This paper will address not only these areas but also the relationship between material control and other safeguards and security functions

  3. Burnup Measurement of Spent Fuel Assembly by CZT-based Gamma-ray Spectroscopy for Input Nuclear Material Accountancy of Pyroprocessing

    International Nuclear Information System (INIS)

    Seo, Hee; Oh, Jong-Myeong; Shin, Hee-Sung; Kim, Ho-Dong; Lee, Seung-Kyu; Park, Se-Hwan

    2013-06-01

    Input nuclear material accountancy is crucial for a pyroprocessing facility safeguards. Until a direct Pu measurement technique is established, an indirect method based on code calculations with burnup measurement and neutron counting for 244 Cm could be a practical option. Burnup can be determined by destructive analysis (DA) for final dispositive accuracy or by nondestructive assay (NDA) for near-real time accountancy. In the present study, an underwater burnup measurement system based on gamma-ray spectroscopy with the CZT detector was developed and tested on a spent fuel assembly. Burnup was determined according to the 134 Cs/ 137 Cs activity ratio with efficiency correction by Geant4 Monte Carlo simulations. The activity ratio as a function of burnup was obtained by ORIGEN calculations. The measured burnup error was 8.6%, which was within the measurement uncertainty. It is expected that the underwater burnup measurement system could fulfill an important role as a means of near-real time accountancy at a future pyroprocessing facility. (authors)

  4. Methods of Verification, Accountability and Control of Special Nuclear Material

    International Nuclear Information System (INIS)

    Stewart, J.E.

    1999-01-01

    This session demonstrates nondestructive assay (NDA) measurement, surveillance and analysis technology required to protect, control and account (MPC and A) for special nuclear materials (SNM) in sealed containers. These measurements, observations and analyses comprise state-of-the art, strengthened, SNM safeguards systems. Staff member specialists, actively involved in research, development, training and implementation worldwide, will present six NDA verification systems and two software tools for integration and analysis of facility MPC and A data

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

    International Nuclear Information System (INIS)

    Crawford, D.W.

    1996-01-01

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

  6. Consequences of Illicit Trafficking of Nuclear or Other Radioactive Materials

    International Nuclear Information System (INIS)

    Moore, G.M.

    2010-01-01

    Explosion of a nuclear yield device is probably the worst consequence of Illicit Trafficking of nuclear or other radioactive materials.The nuclear yield device might be a stolen nuclear weapon, or an improvised nuclear device. An improvised nuclear device requires nuclear material design, and construction ability. Use of a radioactive dispersal device probably would not result in large numbers of casualties.However economic losses can be enormous. Non-Technical effects of nuclear trafficking (e.g. public panic, work disruption, etc.) and political and psychological consequences can far exceed technical consequences

  7. Global risks due to illicit trafficking of nuclear and radiological materials

    International Nuclear Information System (INIS)

    Barakat, M. F.

    2012-01-01

    The global widespread applications of of the peaceful uses of atomic energy resulted in the production and accumulation of huge amounts of dangerous nuclear wastes and nuclear materials, the greater part of which is left either unattended or insufficiently protected. In the mean time, many terrorist groups appeared in the international arena aiming at fighting against all forms of pressure, discrimination or injustice in the international relations among developed and developing countries particularly in politically unstable regions of the world. Unfortunately, these terrorist groups were inclined to adopt the use of nuclear or radiological rather crude weapons to improve their methods and efforts in imposing situations of maximum horror possible to subjected communities. In the present work a brief study of the dimensions of nuclear terrorism, its forms and means directed to its support , has been carried out. The efforts to combat against nuclear proliferation in Central Asia as a region in which most of the violations of the non proliferation efforts occurred has been treated. In contrast, the prevailing conditions and efforts in the Americas region are discussed being a region in which combined efforts of the united states with other American countries were rather successful in combating nuclear proliferation. Some recommendations have been given concerning the necessary measures to face the global risk of illicit trafficking of nuclear materials all over the world. (author)

  8. Design and manufacturing of nuclear non destructive measurement systems and coupled metrology in order to quantify the radionuclides contaminating the wastes and the processes of the nuclear industry

    International Nuclear Information System (INIS)

    Saurel, N.

    2013-01-01

    The non-destructive nuclear measurement has to provide responses for the main challenges of the nuclear industry such as nuclear facility safety, health, environmental impact, performance, reliability and cost control. The goal of the non-destructive nuclear measurement is to characterize, without any deterioration, an object contaminated by one or more radionuclides. The passive or active nuclear measurement are utilized for quantifying the radionuclides in the effluents, the liquid and solid wastes and the nuclear material hold-up. It is also deployed for the process control. In this case, it is a standard production control but, the most of the time, it controls the validity of the safety domain of the production unit. The results of these measurements are used to establish the radiological inventory or the nuclear material balance. The radiological inventory is needed for the nuclear wastes outlets while the nuclear material balance is needed to follow through with the criticality units. The most important objective is to give the quantitative and/or qualitative value and its uncertainty are confident of the radionuclides contaminating the object. This contaminated object might be of different geometrical shapes, sizes or physico-chemical compositions. In order to be efficient, the non-destructive nuclear measurement has to include the apparatus, the measurement actions, the settings and the use of the coupled methodologies. I relate, in this memoir, my main research and development works that I drove or in which I took part for achieving these goals. These works are about the metrology of nuclear radiations and are used in three main types of measurement which are the gamma spectrometry, the alpha spectrometry and the passive or active neutron counting. (author) [fr

  9. The changing role of nuclear materials accounting

    International Nuclear Information System (INIS)

    Gibbs, P.W.

    1995-01-01

    Nuclear materials accounting and accounting systems at what have been DOE Production sites are evolving into management decision support tools. As the sites are moving into the mode of making decisions on how to disposition complex and varied nuclear material holdings, the need for complete and many times different information has never been greater. The artificial boundaries that have historically been established between what belongs in the classic material control and accountability (MC and A) records versus what goes into the financial, radiological control, waste, or decommissioning and decontamination records are being challenged. In addition, the tools historically used to put material into different categories such as scrap codes, composition codes, etc. have been found to be inadequate for the information needs of today. In order to be cost effective and even, more importantly to effectively manage -our inventories, the new information systems the authors design have to have the flexibility to serve many needs. In addition, those tasked with the responsibility of managing the inventories must also expand beyond the same artificial boundaries. This paper addresses some of the things occurring at the Savannah River Site to support the changing role of nuclear materials accounting

  10. Steps to implement the legal and regulatory infrastructure for physical protection of nuclear material in Peru

    International Nuclear Information System (INIS)

    Ramirez Quijada, R.

    2001-01-01

    Full text: The signature of Peru to become part of the Convention of Physical Protection of Nuclear Material in 1995 has implied an obligation to formalize the legal and regulatory infrastructure for this purpose. As first step, physical protection measures were formalized on the two nuclear facilities: one critical assembly of zero power (RP0) and another research reactor of 10 Mw thermal power (RP10). Both of the installations use low enriched uranium nuclear fuel (Material and Testing Material - MTR type). On the other side, even thorium was put in perspective to control; currently it is being used for non-nuclear purposes and has not been included inside the physical protection measures. Its physical and chemical form and its small quantity do not warrant for applying the Convention. The physical protection measures implemented in the research reactor are well depicted and it is concluded that the physical protection system meets the recommendations of INFCIRC/225/Rev.3. The critical facility (RP0), as having nuclear material categorized III, has implemented a less restrictive system but enough to meet the requirements. In 1999 an evaluation of all physical protection systems was performed for these two nuclear installations. This evaluation took into account the recommendations of INFCIRC/225/Rev.4. The general conclusion was that the performance of physical protection system was suitable to the categories of nuclear material - II and III - and that the installations where nuclear material is used were suitably protected against non-authorized or illegal removal of nuclear material and sabotage. However, some of components of the system were not appropriately working and could make all of the system weak. Another of the identified problems was the lack of a rule on physical protection and also the lack of the Design Basis Threat, although this fact was well known due the social conditions in the country. The second undertaking has been to prepare the rule on

  11. Test and evaluation of computerized nuclear material accounting methods. Final report

    International Nuclear Information System (INIS)

    1995-01-01

    In accordance with the definition of a Material Balance Area (MBA) as a well-defined geographical area involving an Integral operation, the building housing the BFS-1 and BFS-1 critical facilities is considered to consist of one MBA. The BFS materials are in the form of small disks clad in stainless steel and each disk with nuclear material has its own serial number. Fissile material disks in the BFS MBA can be located at three key monitoring points: BFS-1 facility, BFS-2 facility and main storage of BFS fissile materials (storage 1). When used in the BFS-1 or BFS-2 critical facilities, the fissile material disks are loaded in tubes (fuel rods) forming critical assembly cores. The following specific features of the BFS MBA should be taken into account for the purpose of computerized accounting of nuclear material: (1) very large number of nuclear material items (about 70,000 fissile material items); and (2) periodically very intensive shuffling of nuclear material items. Requirements for the computerized system are determined by basic objectives of nuclear material accounting: (1) providing accurate information on the identity and location of all items in the BFS material balance area; (2) providing accurate information on location and identity of tamper-indicating devices; (3) tracking nuclear material inventories; (4) issuing periodic reports; (5) assisting with the detection of material gains or losses; (6) providing a history of nuclear material transactions; (7) preventing unauthorized access to the system and data falsification. In August 1995, the prototype computerized accounting system was installed on the BFS facility for trial operation. Information on two nuclear material types was entered into the data base: weapon-grade plutonium metal and 36% enriched uranium dioxide. The total number of the weapon-grade plutonium disks is 12,690 and the total number of the uranium dioxide disks is 1,700

  12. Methods for nuclear material control used in the basic production of a typical radiochemical plant

    International Nuclear Information System (INIS)

    Kositsyn, V.F.; Mukhortov, N.F.; Korovin, Yu.I.; Rudenko, V.S.; Petrov, A.M.

    1999-01-01

    Techniques for destructive and non-destructive assay of the component and isotopic composition of nuclear materials are described, namely gravimetric, titrimetric, coulometric, mass spectrometry, as well as those based on registration of neutron and γ radiations. Their metrologic characteristics are described. The techniques described are suggested to be used for nuclear material (NM) control and accounting purposes at the model radiochemical plant for processing irradiated fuel subassemblies from power reactors. The measurement control program is also described. This program is intended for the measurement quality assurance in the framework of NM control and accountancy system [ru

  13. Evaluating the Aspect of Nuclear Material in Fuel Cycles

    Energy Technology Data Exchange (ETDEWEB)

    Takagi, Shunsuke; Pickett, Susan; Oda, Takuji; Choi, Jor-Shan; Kuno, Yusuke; Takana, Satoru [Department of Nuclear Engineering and Management, The University of Tokyo, 7-3-1 Hongo, Bunkyo-ku, Tokyo 113-8685 (Japan); Nagasaki, Shinya [Nuclear Professional School, The University of Tokyo (Japan)

    2009-06-15

    The increasing number of countries that wish to introduce nuclear power plants raises attention to proliferation resistance in nuclear power plants, and nuclear fuel cycle facilities. In order to achieve adequate proliferation resistance, it is important to evaluate it and to construct effective international institutional frameworks as well as technologies involving high level of proliferation resistance. Although some methods have been proposed for evaluation of the proliferation resistance, their validities have not been investigated in detail. In the present paper, therefore, we compare some of the proposed methodologies. It is essential to detect the abuse or diversion of nuclear material before the nuclear explosive device can be manufactured in order to prevent proliferation. The time needed for the detection of material primary depends on the safeguards that the country applies, and the time needed for fabrication mainly depends on the attributes of the nuclear material. Hence, we divided the proliferation resistance into two parts: the level of safeguards and the material. For examination of evaluation methods such as the one proposed by Charlton [1] or the figure of merit (FOM) [2], sensitivity analysis was performed on weighting factors and scenarios. The validity and characteristics of each method were discussed, focusing on the applicability of each method to the assessment of multi-national approaches such as GNEP. [1] W. S. Charlton, R. L. LeBouf, C. Gariazzo, D. G. Ford, C. Beard, S. Landeberger, M. Whitaker, 'Proliferation resistance assessment methodology for nuclear fuel cycles', Nuclear Technology, 157, 1 (2007). [2] C.G. Bathke et al, 'An assessment of the proliferation resistance of materials in advanced nuclear fuel cycles', 8. International Conference on Facility Operations (2008). (authors)

  14. Control and Management of Small Quantity Nuclear Material (SQNM) on Safeguards

    International Nuclear Information System (INIS)

    Park, Jae Hwan; Shin, Byung Woo; Park, Jae Beom

    2009-01-01

    Small Quantity Nuclear Material (SQNM) is defined as the nuclear material that is below the amount approved in atomic energy act. SQNM generally lists depleted uranium (DU) used as a catalyst or shielding material in exposure devices in industries. The SQNM users have a duty to report information on possessing and using SQNM regularly to the government. All nuclear materials must be included in IAEA reporting lists according to safeguards agreement and additional protocol regardless of amount. However, it is difficult to investigate the status of nuclear material possessed in industries because SQNM is excepted regulation item list in atomic energy act. Most SQNM user industries are small companies so they have some problems like the loss of nuclear material after bankruptcy. Even though the damage of radiation leakage is very low, loss or careless management of nuclear material causes confusion. Thus, developing a control and management system for SQNM is essential. This paper discusses the present condition and prospect of control and management SQNM in Korea

  15. Some issues on the Law for the Regulations of Nuclear Source Material, Nuclear Fuel Material and Reactors Amendment after JCO criticality accident

    International Nuclear Information System (INIS)

    Tanabe, Tomoyuki

    2001-01-01

    As the Amendment of the Law for the Regulation of Nuclear Material, Nuclear Fuel Material and Reactors on an opportunity of the JCO criticality accident can be almost evaluated at a viewpoint of upgrading on effectiveness of safety regulation, it is thought to remain a large problem to rely on only enforcement of regulation due to amendment of the Law at future accident. In future, it can be also said to be important subjects to further expand a philosophy on the regulation (material regulation) focussed to hazards of nuclear material itself, not only to secure effectiveness on the multi-complementary safety regulation due to the administrative agency and the Nuclear Safety Commission but also to prepare a mechanism reflexible of a new information to the safety regulation, and to prepare a mechanism to assist adequate business execution and so forth of enterprises. (G.K.)

  16. Chemical characterization of materials relevant to nuclear technology using neutron and proton based nuclear analytical methods

    International Nuclear Information System (INIS)

    Acharya, R.

    2014-01-01

    Nuclear analytical techniques (NATs), utilizing neutron and proton based nuclear reactions and subsequent measurement of gamma rays, are capable of chemical characterization of various materials at major to trace concentration levels. The present article deals with the recent developments and applications of conventional and k0-based internal monostandard (i) neutron activation analysis (NAA) and (ii) prompt gamma ray NAA (PGNAA) methods as well as (iii) in situ current normalized particle induced gamma ray emission (PIGE). The materials that have been analyzed by NAA and PGNAA include (i) nuclear reactor structural materials like zircaloys, stainless steels, Ni alloys, high purity aluminium and graphite and (ii) uranium oxide, U-Th mixed oxides, uranium ores and minerals. Internal monostandard NAA (IM-NAA) method with in situ detection efficiency was used to analyze large and non-standard geometry samples and standard-less compositional characterization was carried out for zircaloys and stainless steels. PIGE methods using proton beams were standardized for quantification of low Z elements (Li to Ti) and applied for compositional analysis of borosilicate glass and lithium titanate (Li 2 TiO 3 ) samples and quantification of total B and its isotopic composition of B ( 10 B/ 11 B) in boron based neutron absorbers like B 4 C. (author)

  17. Nuclear reactions and self-shielding effects of gamma-ray database for nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Fujita, Mitsutane; Noda, Tetsuji [National Research Institute for Metals, Tsukuba, Ibaraki (Japan)

    2001-03-01

    A database for transmutation and radioactivity of nuclear materials is required for selection and design of materials used in various nuclear reactors. The database based on the FENDL/A-2.0 on the Internet and the additional data collected from several references has been developed in NRIM site of 'Data-Free-Way' on the Internet. Recently, the function predicted self-shielding effect of materials for {gamma}-ray was added to this database. The user interface for this database has been constructed for retrieval of necessary data and for graphical presentation of the relation between the energy spectrum of neutron and neutron capture cross section. It is demonstrated that the possibility of chemical compositional change and radioactivity in a material caused by nuclear reactions can be easily retrieved using a browser such as Netscape or Explorer. (author)

  18. Nuclear reactions and self-shielding effects of gamma-ray database for nuclear materials

    International Nuclear Information System (INIS)

    Fujita, Mitsutane; Noda, Tetsuji

    2001-01-01

    A database for transmutation and radioactivity of nuclear materials is required for selection and design of materials used in various nuclear reactors. The database based on the FENDL/A-2.0 on the Internet and the additional data collected from several references has been developed in NRIM site of 'Data-Free-Way' on the Internet. Recently, the function predicted self-shielding effect of materials for γ-ray was added to this database. The user interface for this database has been constructed for retrieval of necessary data and for graphical presentation of the relation between the energy spectrum of neutron and neutron capture cross section. It is demonstrated that the possibility of chemical compositional change and radioactivity in a material caused by nuclear reactions can be easily retrieved using a browser such as Netscape or Explorer. (author)

  19. The Application of materials attractiveness in a graded approach to nuclear materials security

    Energy Technology Data Exchange (ETDEWEB)

    Ebbinghaus, B. [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, CA 94551 (United States); Bathke, C. [Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, NM 87545 (United States); Dalton, D.; Murphy, J. [National Nuclear Security Administration, US Department of Energy, 1000 Independent Ave., S. W. Washington, DC 20585 (United States)

    2013-07-01

    The threat from terrorist groups has recently received greater attention. In this paper, material quantity and material attractiveness are addressed through the lens of a minimum security strategy needed to prevent the construction of a nuclear explosive device (NED) by an adversary. Nuclear materials are placed into specific security categories (3 or 4 categories) , which define a number of security requirements to protect the material. Materials attractiveness can be divided into four attractiveness levels, High, Medium, Low, and Very Low that correspond to the utility of the material to the adversary and to a minimum security strategy that is necessary to adequately protect the nuclear material. We propose a graded approach to materials attractiveness that recognizes for instance substantial differences in attractiveness between pure reactor-grade Pu oxide (High attractiveness) and fresh MOX fuel (Low attractiveness). In either case, an adversary's acquisition of a Category I quantity of plutonium would be a major incident, but the acquisition of Pu oxide by the adversary would be substantially worse than the acquisition of fresh MOX fuel because of the substantial differences in the time and complexity required of the adversary to process the material and fashion it into a NED.

  20. Risk ranking of LANL nuclear material storage containers for repackaging prioritization.

    Science.gov (United States)

    Smith, Paul H; Jordan, Hans; Hoffman, Jenifer A; Eller, P Gary; Balkey, Simon

    2007-05-01

    Safe handling and storage of nuclear material at U.S. Department of Energy facilities relies on the use of robust containers to prevent container breaches and subsequent worker contamination and uptake. The U.S. Department of Energy has no uniform requirements for packaging and storage of nuclear materials other than those declared excess and packaged to DOE-STD-3013-2000. This report describes a methodology for prioritizing a large inventory of nuclear material containers so that the highest risk containers are repackaged first. The methodology utilizes expert judgment to assign respirable fractions and reactivity factors to accountable levels of nuclear material at Los Alamos National Laboratory. A relative risk factor is assigned to each nuclear material container based on a calculated dose to a worker due to a failed container barrier and a calculated probability of container failure based on material reactivity and container age. This risk-based methodology is being applied at LANL to repackage the highest risk materials first and, thus, accelerate the reduction of risk to nuclear material handlers.

  1. Opening statement at the international conference on security of nuclear material and radioactive sources. Stockholm, 7 May 2001

    International Nuclear Information System (INIS)

    ElBaradei, M.

    2001-01-01

    The opening statement highlights activities of the IAEA in ensuring that nuclear technologies and materials are used only for peaceful purposes; in prevention of illicit trafficking in nuclear and radioactive material; in assistance in development of security measures for these materials; in training of customs officers from Member States in radiation monitoring. It also briefly describes the IAEA safeguards programme

  2. Development of stainless steels for nuclear power plant - Advanced nuclear materials development -

    International Nuclear Information System (INIS)

    Hong, Jun Hwa; Ryu, Woo Seog; Chi, Se Hwan; Lee, Bong Sang; Oh, Yong Jun; Byun, Thak Sang; Oh, Jong Myung

    1994-07-01

    This report reviews the status of R and D and the material specifications of nuclear components in order to develop the stainless steels for nuclear applications, and the technology of computer-assisted alloy design is developed to establish the thermodynamic data of Fe-Cr-Ni-Mo-Si-C-N system which is the basic stainless steel systems. High strength and corrosion resistant stainless steels, 316LN and super clean 347, are developed, and the manufacturing processes and heat treatment conditions are determined. In addition, a martensitic steel is produced as a model alloy for turbine blade, and characterized. The material properties showed a good performance for nuclear applications. (Author)

  3. Nuclear Security Systems and Measures for Major Public Events. Implementing Guide (Russian Edition)

    International Nuclear Information System (INIS)

    2014-01-01

    Terrorism remains a threat to international stability and security. High profile international and national major public events occur regularly, capturing great public interest and receiving intense media coverage. It is widely acknowledged that there is a substantial threat of a terrorist attack on major public events such as high profile political or economic summit meetings or major sporting contests. The threat of nuclear and radiological terrorism remains on the international security agenda. Nevertheless, to reduce this risk, the international community has made great progress in securing nuclear and other radioactive material that could otherwise be used in a terrorist act. This progress is contingent on the efforts of all States to adopt strong nuclear security systems and measures. There are large quantities of diverse radioactive material in existence, which are used in areas such as health, the environment, agriculture and industry. The hazards of this material vary according to composition and intensity. Additionally, the use of explosives in combination with this material can drastically enhance the impact of a criminal or terrorist act. If a criminal or terrorist group managed to detonate a so-called 'dirty' bomb in an urban area, the result could be mass panic, widespread radioactive contamination and major economic and social disruption. Major public events are seldom held in the same State or at the same location or even at the same venue. At the national level, the hosting of major public events with proper nuclear security arrangements can provide a foundation on which to build an enduring national framework for nuclear security; one that can exist long after the event. The organization of a major public event in which large numbers of people congregate presents complex security challenges for the State hosting such an event. Criminal or terrorist acts involving nuclear or other radioactive material at any major public event could result in

  4. Nuclear materials identification by photon interrogation

    International Nuclear Information System (INIS)

    Pozzi, S.A.; Monville, M.; Padovani, E.

    2005-01-01

    We describe a preliminary modification to the Monte Carlo codes MCNP-X and MCNP-PoliMi that is aimed at simulating the neutron and photon field generated by interrogating fissile (and non-fissile) material with a high energy photon source. Photo-atomic and photo-nuclear collisions are modeled, with particular emphasis on the generation of secondary particles that are emitted as a result of these interactions. The simulations can be used to design and analyze measurements that are performed in a wide variety of scenarios. An application of the methodology to the interrogation of packages on a luggage belt conveyor is presented. Preliminary results show that it is possible to detect 5 Kg of highly enriched uranium in a package by measuring the correlation function between 2 detectors. This correlation function is based on the detection of prompt radiation from photonuclear events

  5. Accounting for and control of nuclear material at the Central Institute of Nuclear Research, Rossendorf

    International Nuclear Information System (INIS)

    Heidel, S.; Rossbander, W.; Helming, M.

    1983-01-01

    A survey is given of the system of accounting for and control of nuclear material at the Central Institute for Nuclear Research, Rossendorf. It includes 3 material balance areas. Control is implemented at both the institute and the MBA levels on the basis of concepts which are coordinated with the national control authority of the IAEA. The system applied enables national and international nuclear material control to be carried out effectively and economically at a minimum of interference with operational procedures. (author)

  6. New materials options for nuclear systems

    International Nuclear Information System (INIS)

    Jones, R.H.; Garner, F.A.; Bruemmer, S.M.; Gelles, D.S.

    1989-01-01

    Development of new materials for nuclear reactor systems is continuing to produce options for improved reactor designs. Materials with reduced environment-induced crack growth is a key materials issue for the light water reactor (LWR) industry while the development of low activation ferritic, austenitic and vanadium alloys has been an active area for materials development for fusion reactor structural applications. Development of advanced materials such as metal matrix and ceramic matrix composites for reactor systems have received a limited amount of attention. (author)

  7. Some technical aspects of the nuclear material accounting and control at nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Miller, O.A.; Babaev, N.S.; Gryazev, V.M.; Gadzhiev, G.I.; Gabeskiriya, V.Ya.

    1977-01-01

    The possibilities of nuclear material accounting and control are discussed at nuclear facilities of fuel cycle (WWER-type reactor, fuel fabrication plant, reprocessing plant and uranium enrichment facility) and zero energy fast reactor facility. It is shown that for nuclear material control the main method is the accounting with the application isotopic correlations at the reprocessing plant and enrichment facility. Possibilities and limitations of the application of destructive and non-destructive methods are discussed for nuclear material determinations at fuel facilities and their role in the accounting and safeguards systems as well as possibilities of the application of neutron method at a zero energy fast reactor facility [ru

  8. Development and implementation of methods for determination of the origin of nuclear materials

    International Nuclear Information System (INIS)

    Wallenius, M.; Pajo, L.; Mayer, K.

    2001-01-01

    The determination of the origin of seized nuclear material is important for authorities in the context of the criminal investigation, in order to return the material to its last legal owner and to help preventing any further diversion of material from this source. Origin determination is based on a complex pattern of parameters obtained through analytical measurements. The information required to determine the origin of nuclear materials may be divided into two categories: endogenous information (e.g. age or mode of production of the material) which is self-explanatory; whereas exogenous information (e.g. dimensions, surface roughness, impurities) requires a database to which the parameters can be compared. The Institute for Transuranium Elements has developed methods to determine characteristic parameters like impurities, surface roughness, or microstructural information. Furthermore, a database was set up containing relevant information on reactor fuels. (author)

  9. Basic research for nuclear energy. y Study on the nuclear materials technology

    Energy Technology Data Exchange (ETDEWEB)

    Kuk, I H; Lee, H S; Jeong, Y H; Sung, K W; Han, J H; Lee, J T; Lee, H K; Kim, S J; Kang, H S; An, D H; Kim, K R; Park, S D; Han, C H; Jung, M K; Oh, Y J; Kim, K H; Kim, S H; Back, J H; Kim, C H; Lim, K S; Kim, Y Y; Na, J W; Ku, J H; Lee, D H

    1996-12-01

    A study on the nuclear materials technologies which are necessary to establish the base for alloy development was performed. - The feasibility study on the application of Zircaloy scrap waste for hydrogen storage - The development of metal hydride battery for energy storage system - The establishment of transmission electron microscopy database for nuclear materials - The basic technology for the development of cladding materials for high burnup - The water chemistry technology for secondary system pH control and the photocatalysis technology for decomposition and removal of organics. - Improvement of primary component integrity of PWR by Zinc injection. (author). 175 refs., 58 tabs., 262 figs.

  10. Basic research for nuclear energy. y Study on the nuclear materials technology

    International Nuclear Information System (INIS)

    Kuk, I. H.; Lee, H. S.; Jeong, Y. H.; Sung, K. W.; Han, J. H.; Lee, J. T.; Lee, H. K.; Kim, S. J.; Kang, H. S.; An, D. H.; Kim, K. R.; Park, S. D.; Han, C. H.; Jung, M. K.; Oh, Y. J.; Kim, K. H.; Kim, S. H.; Back, J. H.; Kim, C. H.; Lim, K. S.; Kim, Y. Y.; Na, J. W.; Ku, J. H.; Lee, D. H.

    1996-12-01

    A study on the nuclear materials technologies which are necessary to establish the base for alloy development was performed. - The feasibility study on the application of Zircaloy scrap waste for hydrogen storage - The development of metal hydride battery for energy storage system - The establishment of transmission electron microscopy database for nuclear materials - The basic technology for the development of cladding materials for high burnup - The water chemistry technology for secondary system pH control and the photocatalysis technology for decomposition and removal of organics. - Improvement of primary component integrity of PWR by Zinc injection. (author). 175 refs., 58 tabs., 262 figs

  11. Safeguarding nuclear weapon: Usable materials in Russia

    International Nuclear Information System (INIS)

    Cochran, T.

    1998-01-01

    Both the United States and Russia are retaining as strategic reserves more plutonium and HEU for potential reuse as weapons, than is legitimately needed. Both have engaged in discussions and have programs in various stages of development to dispose of excess plutonium and HEU. These fissile material disposition programs will take decades to complete. In the interim there will be, as there is now, hundreds of tons of separated weapon-usable fissile material stored in tens of thousands of transportable canisters, each containing from a few to several tons of kgs of weapon-usable fissile material. This material must be secured against theft and unauthorized use. To have high confidence that the material is secure, one must establish criteria against which the adequacy of the protective systems can be judged. For example, one finds such criteria in US Nuclear Regulatory Commission (USNRC) regulations for the protection of special nuclear materials

  12. 235Uranium isotope abundance certified reference material for gamma spectrometry EC nuclear reference material 171 certification report

    International Nuclear Information System (INIS)

    De Bievre, P.; Eschbach, H.L.; Lesser, R.; Meyer, H.; Audenhove, Van J.

    1986-01-01

    This certification report contains the information necessary for the final certification of EC nuclear reference material 171. It is also intended to inform the user of the reference material concerned on technical/scientific details which are not given in the certificate. The report describes the reference material which consists of sets of U 3 O 8 samples with five different 235 U/U abundances, filled in cylindrical aluminium cans. The can bottom serves as window for emitted gamma radiation. The report describes how the 235 U/U abundances were characterized, how the other properties relevant for gamma measurements were determined and gives all connected results as well as those from the verification measurements. Appendix A represents the draft certificate. 32 refs

  13. Development of a computerized nuclear materials control and accounting system for a fuel reprocessing plant

    International Nuclear Information System (INIS)

    Crawford, J.M.; Ehinger, M.H.; Joseph, C.; Madeen, M.L.

    1979-07-01

    A computerized nuclear materials control and accounting system (CNMCAS) for a fuel reprocessing plant is being developed by Allied-General Nuclear Services at the Barnwell Nuclear Fuel Plant. Development work includes on-line demonstration of near real-time measurement, measurement control, accounting, and processing monitoring/process surveillance activities during test process runs using natural uranium. A technique for estimating in-process inventory is also being developed. This paper describes development work performed and planned, plus significant design features required to integrate CNMCAS into an advanced safeguards system

  14. Control and accountancy of nuclear materials in a uranium enrichment plant

    International Nuclear Information System (INIS)

    Hurt, N.H.

    1985-01-01

    A nuclear material control and accountancy system has been developed by Goodyear Atomic Corporation to meet safeguards and security requirements. It comprises three major elements: physical security, nuclear material control, and nuclear material accounting. This safeguards system is called Dynamic Material Control and Accountancy System (DYMCAS). The system approaches real-time computer control on a transaction-by-transaction basis

  15. Development of the method for the dimensional measurement of the HANARO nuclear fuel

    International Nuclear Information System (INIS)

    Kim, Tae Yeon; Lee, K. S.; Park, D. G.; Choo, Y. S.; Ahn, S. B.

    1998-06-01

    Dimension of the nuclear fuel is altered in nuclear reactor because of the neutron exposure with high pressure water. If the deformation is overlarge, the severe problem in safety of the nuclear fuel and the reactor come about. Therefore the accurate dimensional data of the nuclear fuel in diameter and length is very important for the design of the nuclear fuel and the estimation of the nuclear safety. Measurement of diameter for the dummy HANARO fuel rod which has not filled with real fuel material was carried out in hot cell. And also the length of the HANARO fuel assembly and the rod are measured. Dimensional measuring method for the HANARO fuel was developed. The test result show our method is good enough to distinguish change in volume with statistical uncertainty of 0.6 %. (author). 2 refs., 7 tabs., 20 figs

  16. Application of nuclear track detectors for radon related measurments

    International Nuclear Information System (INIS)

    Abu-Jarad, F.A.

    1988-01-01

    The application of nuclear track detectors for radon related measurements is discussed. The ''Can Technique'', used for measuring radon emanation from building materials, walls and soil; the ''Working Level Monitor'', used for measuring short period working levels of radon daughters in houses; and ''Passive Radon Dosimeters'', used to measure radon levels in houses for long term (few months) periods are described. Application of nuclear track detectors for measuring the radon daughters plate-out on the surface of mixing fan blades and walls are discussed. The uranium content of some wall papers was found to be 6 ppm. The variation of radon progeny concentration in the same room was measured and supported by another study through Gas Chromatograph measurements. The independence of radon concentration on room level in high-rise buildings was established. The effect of sub-floor radon emanation on radon concentration in houses is dependent on whether there is sub-floor ventilation or not. (author)

  17. Accounting systems for special nuclear material control. Technical report

    International Nuclear Information System (INIS)

    Korstad, P.A.

    1980-05-01

    Nuclear material accounting systems were examined and compared to financial double-entry accounting systems. Effective nuclear material accounting systems have been designed using the principles of double-entry financial accounting. The modified double-entry systems presently employed are acceptable if they provide adequate control over the recording and summarizing of transactions. Strong internal controls, based on principles of financial accounting, can help protect nuclear materials and produce accurate, reliable accounting data. An electronic data processing system can more accurately maintain large volumes of data and provide management with more current, reliable information

  18. Defense Nuclear Material Stewardship Integrated Inventory Information Management System (IIIMS).

    Energy Technology Data Exchange (ETDEWEB)

    Aas, Christopher A.; Lenhart, James E.; Bray, Olin H.; Witcher, Christina Jenkin

    2004-11-01

    Sandia National Laboratories was tasked with developing the Defense Nuclear Material Stewardship Integrated Inventory Information Management System (IIIMS) with the sponsorship of NA-125.3 and the concurrence of DOE/NNSA field and area offices. The purpose of IIIMS was to modernize nuclear materials management information systems at the enterprise level. Projects over the course of several years attempted to spearhead this modernization. The scope of IIIMS was broken into broad enterprise-oriented materials management and materials forecasting. The IIIMS prototype was developed to allow multiple participating user groups to explore nuclear material requirements and needs in detail. The purpose of material forecasting was to determine nuclear material availability over a 10 to 15 year period in light of the dynamic nature of nuclear materials management. Formal DOE Directives (requirements) were needed to direct IIIMS efforts but were never issued and the project has been halted. When restarted, duplicating or re-engineering the activities from 1999 to 2003 is unnecessary, and in fact future initiatives can build on previous work. IIIMS requirements should be structured to provide high confidence that discrepancies are detected, and classified information is not divulged. Enterprise-wide materials management systems maintained by the military can be used as overall models to base IIIMS implementation concepts upon.

  19. Nuclear Security Recommendations on Nuclear and other Radioactive Material out of Regulatory Control: Recommendations (Spanish Edition)

    International Nuclear Information System (INIS)

    2012-01-01

    This publication presents recommendations for the nuclear security of nuclear and other radioactive material that is out of regulatory control. It is based on national experiences and practices and guidance publications in the field of security as well as the nuclear security related international instruments. The recommendations include guidance for States with regard to the nuclear security of nuclear and other radioactive material that has been reported as being out of regulatory control as well as for material that is lost, missing or stolen but has not been reported as such, or has been otherwise discovered. In addition, these recommendations adhere to the detection and assessment of alarms and alerts and to a graded response to criminal or unauthorized acts with nuclear security implications.

  20. Nuclear Security Recommendations on Nuclear and Other Radioactive Material out of Regulatory Control: Recommendations (Arabic Edition)

    International Nuclear Information System (INIS)

    2012-01-01

    This publication presents recommendations for the nuclear security of nuclear and other radioactive material that is out of regulatory control. It is based on national experiences and practices and guidance publications in the ? field of security as well as the nuclear security related international instruments. The recommendations include guidance for States with regard to the nuclear security of nuclear and other radioactive material that has been reported as being out of regulatory control as well as for material that is lost, missing or stolen but has not been reported as such, or has been otherwise discovered. In addition, these recommendations adhere to the detection and assessment of alarms and alerts and to a graded response to criminal or unauthorized acts with nuclear security implications.