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Sample records for accountability nuclear materials

  1. Nuclear material accounting handbook

    International Nuclear Information System (INIS)

    The handbook documents existing best practices and methods used to account for nuclear material and to prepare the required nuclear material accounting reports for submission to the IAEA. It provides a description of the processes and steps necessary for the establishment, implementation and maintenance of nuclear material accounting and control at the material balance area, facility and State levels, and defines the relevant terms. This handbook serves the needs of State personnel at various levels, including State authorities, facility operators and participants in training programmes. It can assist in developing and maintaining accounting systems which will support a State's ability to account for its nuclear material such that the IAEA can verify State declarations, and at the same time support the State's ability to ensure its nuclear security. In addition, the handbook is useful for IAEA staff, who is closely involved with nuclear material accounting. The handbook includes the steps and procedures a State needs to set up and maintain to provide assurance that it can account for its nuclear material and submit the prescribed nuclear material accounting reports defined in Section 1 and described in Sections 3 and 4 in terms of the relevant agreement(s), thereby enabling the IAEA to discharge its verification function as defined in Section 1 and described in Sections 3 and 4. The contents of the handbook are based on the model safeguards agreement and, where applicable, there will also be reference to the model additional protocol. As a State using The handbook consists of five sections. In Section 1, definitions or descriptions of terms used are provided in relation to where the IAEA applies safeguards or, for that matter, accounting for and control of nuclear material in a State. The IAEA's approach in applying safeguards in a State is also defined and briefly described, with special emphasis on verification. In Section 2, the obligations of the State

  2. Safeguards and nuclear material accounting

    International Nuclear Information System (INIS)

    The safeguards activities performed under INFCIRC/153 type of agreements are often characterized as traditional safeguards. This approach contains three elements: nuclear material accountancy; containment and surveillance measures; and on-site inspections. The nuclear material accountancy establishes the quantity of nuclear material present and changes in that over a period of time. Containment and surveillance measures take advantage of physical boundaries like walls, containers, cameras and seals to restrict, control or monitor the movement of or access to nuclear material. On-site inspection verifies the credibility of the first two verification elements. When we consider accounting of nuclear material we must have in our mind a Material Balance Area (MBA) separated by a physical boundary. There should be a close accounting period and also a nuclear material to account for. If there is some beginning inventory (BPI) in the MBA, it might receipt some material say R from other source. Then after processing some end product say S has been transferred to other MBA. During the process some part of the material can not be used further so it has to be discarded after measurement. Let it be MD. At the end of period some part of the material is still left over in the MBA, call it EPI. Since the nuclear materials are of high monitory and strategic value. The objective of their accounting and control is the timely detection of diversion of significant quantities of nuclear material from peaceful nuclear activities - to the manufacture of nuclear weapons or of other nuclear explosive devices or for purposes unknown, and to deterrence of such diversion by the risk of early detection

  3. The status of KAERI nuclear material accountancy

    Energy Technology Data Exchange (ETDEWEB)

    Park, Ho Joon; Kim, Hyun Sook; Kim, Hyun Jo; Ko, Han Suk; Lee, Byung Doo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2010-10-15

    Nuclear material accountancy within the framework of IAEA safeguards begins with the nuclear material accounting activities by facility operators and the State system of accounting for and control of nuclear material(SSAC), implemented in accordance with the provisions of the safeguards agreement between the IAEA and the State. IAEA verify the correctness of the nuclear material accounting information in the facility records and the reports provided by the SSAC to the IAEA. This paper are described the status of KAERI nuclear material accountancy

  4. Concepts of IAEA nuclear materials accounting

    International Nuclear Information System (INIS)

    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)

  5. 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.

  6. Accountancy, control and protection of nuclear material

    International Nuclear Information System (INIS)

    Clear distribution of responsibilities between the Agency, the States and the operators is fundamental. The Agency has the responsibility to establish and administer safeguards and to assist Member States, upon their request, to develop the means to solve problems arising from the use of atomic energy, one of them being the control of nuclear material. States have the responsibility, in respect to nuclear activities carried out within their territory, under their jurisdiction or under their control anywhere, to define appropriate measures to control nuclear material, to set up an organizational structure to enable the implementation of the measures and to control compliance with the law. This means that States establish systems for ensuring accountancy and control and physical protection of nuclear material. The paper gives an indication of the advice the Agency may give to States, which may request it, in setting up their systems of accountancy and control and physical protection of nuclear material. It also gives some ideas on the co-ordination of the States' systems, the relationship between the States and the Agency in the accountancy and control of nuclear material and the role of the Agency in the physical protection of nuclear material. The present irreplaceable role of the State as a regulatory power is stressed. (author)

  7. Bar code usage in nuclear materials accountability

    International Nuclear Information System (INIS)

    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

  8. The changing role of nuclear materials accounting

    International Nuclear Information System (INIS)

    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

  9. 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.

  10. International safeguards: Accounting for nuclear materials

    International Nuclear Information System (INIS)

    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

  11. Bar code usage in nuclear materials accountability

    International Nuclear Information System (INIS)

    The Oak Ridge Y-12 Plant began investigating the use of automated data collection devices in 1979. At this 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

  12. Bar code application to nuclear material accountancy

    International Nuclear Information System (INIS)

    For the purpose of efficient implementation of IAEA safeguards inspection, operators ought to prepare the information which is related to the strata for flow verification in a timely manner, such as physical inventory listing and summary of the fuel bundles. Today the use of bar code technique in tracing of products related data or counting number of items has been more and more applied to many facets of industry. From these points of view, the Japan Nuclear Fuel Company (NF) has been developing JNF Total Bar Code System. Now JNF has established an on-line input system of the fuel bundle accountability data by use of the bar code system to quickly prepare the information necessary for the inspection. As the first step, JNF implemented this bar code system at the flow verification to prepare physical inventory summary and location map of the fuel bundles in the storage. This paper reports that as a result of this, NF confirmed that this bar code system made it possible to input easily and quickly nuclear material accountancy information, and therefore this system is utilized as an effective and efficient measure of timely preparation for the inspection

  13. 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...

  14. Nuclear material accounting: The next generation

    International Nuclear Information System (INIS)

    The Westinghouse Hanford company (Westinghouse Hanford) and the Los Alamos National Laboratory (LANL) have undertaken a joint effort to develop a new generation material accounting system. The system will incorporate the latest advances in microcomputer hardware, software, and network technology. This system, the Local Area Network Material Accounting System (LANMAS), offers greater performance and functionality at a reduced overall cost. It also offers the possibility of establishing a standard among DOE and NRC facilities for material accounting. This report provides a discussion of this system

  15. Accounting systems for special nuclear material control. Technical report

    International Nuclear Information System (INIS)

    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

  16. Technology development for nuclear material accountability

    International Nuclear Information System (INIS)

    The objective of this study is to contribute efforts to identifying the characteristics and operation reason of known or clandestine nuclear facility. To achieve this purpose is by means of chemical analysis of various samples from process line and surrounding environment. It is possible to assume that the information of the qualitative and quantitative nuclear activities can be obtained by chemically verifying the various samples discharged from specific nuclear facility. Therefore, these techniques may be helpful to identify the presence of undecleared facilities, to detect the falsified operating data and to verify the accounting data. Am-241 dating method is available to detect the actions to conceal the diversion strategy by falsifying operation data of plutonium production facility. Low level counting systems have been used as environmental monitoring in the neighborhood of nuclear facilities, and it is important to optimize experimental conditions (to reduce system background and to improve detection efficiency) for more accurate measurement. These optimized conditions may be useful in establishing low background counting system and counting room. (Author)

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

    Science.gov (United States)

    2013-06-27

    ... COMMISSION Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants AGENCY: Nuclear... Accounting Systems for Nuclear Power Plants.'' This regulatory guide provides guidance on recordkeeping and... nuclear material control and accounting system requirements for nuclear power plants. This guide...

  18. 77 FR 28407 - Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants

    Science.gov (United States)

    2012-05-14

    ... COMMISSION Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants AGENCY: Nuclear...-5028, ``Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants.'' In DG-5028... Control and Accounting Systems for Nuclear Power Plants.'' DATES: Submit comments by July 16,...

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

    Energy Technology Data Exchange (ETDEWEB)

    Taylor, S; Terentiev, V G

    1998-12-01

    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.

  20. International Target Values for Measurement Uncertainties in Nuclear Material Accountancy

    Institute of Scientific and Technical Information of China (English)

    LIU; Hong-bin; GAO; Qiang

    2012-01-01

    <正>The IAEA has published a revised version International Target Values (ITVs) 2010 for Measurement Uncertainties in Safeguarding Nuclear Materials in 2010. The report proposes the international target values of measurement uncertainties of the routine measurement methods for the nuclear material accountancy.

  1. Development of Nuclear Material Accounting and Safeguards Technology

    International Nuclear Information System (INIS)

    This project is aimed at the development of nuclear material accounting and safeguards technology. Nuclear material accountancy technology for an each unit process and nuclear characteristic analysis technology to demonstrate the safeguards technology for a pyroprocessing facility have been developed during the first phase of the project. A study for analyzing the safeguardability of pyroprocessing facility and preliminary evaluation has also been carried out. The safeguards technology system for electro-reduction process has been established to develop the unit process nuclear material accountancy technology through nuclear material accounting in ACPF and performance test of surveillance equipment using spent fuels and neutron source. Nuclear material accountancy measure for electro-refining process where various kinds of nuclear materials are generated compared to electro-reduction process has been constructed, and its performance test has been conducted as well. A Gamma/neutron integrated system has been developed as a nuclear characteristic analysis technology for pyroprocess nuclear material, the possibility of Pu and U measurement has been analyzed using FRAM, and fundamental experiment has been performed to examine whether LIBS technology is applicable to nuclear material accountancy of pyroprocess. A preliminary concept design of safeguards system for pyroprocessing facility and basic design of computer code for analyzing the safeguardability have been carried out to perform the safeguardability analysis and preliminary evaluation for pyroprocessing facility, and a study for analyzing the safeguardability of KAPF which has scale of 100 MT-HM/year has been conducted in collaboration with LANL. Also, an IAEA Member State Support Program for establishing safeguards approach technology for pyroprocessing facility ('Support for Development for a Safeguards Approach for a Pyroprocessing Plant') has been conducting in cooperation with KINAC. It is expected that

  2. 10 CFR 74.31 - Nuclear material control and accounting for special nuclear material of low strategic significance.

    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 low strategic significance. 74.31 Section 74.31 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Special Nuclear Material of...

  3. Nuclear Material Accountancy Assessment Technical Measures in Nuclear Centrifuge Enrichment Facility

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    Nuclear material accountancy assessment is the main technical measures for nuclear materials regulatory. It is an important basis to detect theft, loss and the illegal diversion of nuclear material. In order to implement the control of nuclear materials for nuclear facilities,

  4. Technology development for nuclear material 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 [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-12-01

    Computer code simulation was carried out for Pu contents estimation from the spent fuel discharged from research reactor for the purpose of the effective and efficient support of independent verification of nuclear activity in that reactor. MCNP code was used to find the characteristics of spontaneous fission neutrons and of neutrons produced by (a, n) reaction, and to get the detection probability of neutrons emitted from the spent fuels at the surrounding detectors as a function of energy. 13 figs, 9 tabs, 3 refs. (Author).

  5. Software for MUF evaluating in item nuclear material accounting

    International Nuclear Information System (INIS)

    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. 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...

  7. The development of nuclear material accountability system - software user's manual

    International Nuclear Information System (INIS)

    We have developed the near-real time nuclear material accountability system, named by DMAS, for DUPIC Test Facility in the basis of the survey of DUPIC process and activities for the accountability of the system, and the review of the rules and regulations related to the nuclear material accounting. Our system adopts the structure and technologies used in COREMAS which was developed by LANL. This technical report illustrates the system structure and program usage as a user manual for DMAS. (author). 56 tabs., 1 fig

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

    International Nuclear Information System (INIS)

    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. 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.

  10. Development of nuclear material accounting and safeguards technology

    Energy Technology Data Exchange (ETDEWEB)

    Shin, H. S.; Kim, H. D.; Park, K. J; and others

    2012-04-15

    The objective of this project is to analyze the safeguard ability of pyroprocess facility and to establish the safeguards system for pyroprocess by developing the technology of nuclear material accounting for unit process, surveillance technology and nuclear characteristics analysis technology which are needed to demonstrate the safeguards technology of pyroprocess. In order to establish the nuclear material accountancy for PRIDE the unified NDA was designed by integrating neutron detection, gamma ray detection, and mass measurement. The surveillance system of PRIDE includes gamma ray detector system for tracing the position of nuclear material in PRIDE and the safeguards system was designed considering the characteristics of nuclear material accountancy and surveillance equipment and monitoring the main factors of process equipment. Based on the design of safeguards system for PRIDE a simulation program for the integrated accounting and surveillance information system has been developed and tested. The safeguard ability analysis code for pyroprocessing facility has been designed to develop a Pyroprocessing Material flow and Material Unaccounted For Uncertainty Simulation (PYMUS) program based on the result from safeguard ability analysis by ROK IAEA MSSP. For novel technologies development of nuclear material accountancy by domestic and international cooperation, the application of XRF, SINRD, PNAR, FRAM, LIBS to NMA has been studied. The safeguards system of PRIDE will be referred to verify the safeguards approach and implementation techniques for pyroprocessing facility on international cooperation(ROK US Joint Fuel Cycle Study and ROK IAEA Member State Support Program). The results of this project will contribute to increase the nuclear transparency for realizing the pyroprocessing technology of the ROK as well as to establish the safeguards technology for pyroprocessing facility.

  11. Application of game theory to nuclear material accounting. Final report

    International Nuclear Information System (INIS)

    An approach based upon the theory of games is presented that determines an optimal alarm threshold for detecting unauthorized or deliberate diversion of nuclear material based upon material accounting data. A mathematical model is developed, solved, and applied to a generic nuclear facility. By considering a malevolent diverter as a basic ingredient of the analysis this approach offers advantages over conventional statistical hypothesis testing. The results show that periodic inventories and appropriate interpretation of MUF can provide a high assurance for indicating diversion in a nuclear material safeguards situation. The optimal policy is to select the alarm threshold by a mixed strategy rather than a pre-set single fixed value. Procedures for doing this are presented in the report. With this approach, MUF data by itself may be more useful in indicating possible unauthorized diversion of special nuclear material

  12. Variance and covariance calculations for nuclear materials accounting using ''PROFF''

    International Nuclear Information System (INIS)

    To determine 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 those 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. We have developed an interactive, menu-driven computer program, called PROFF (for PROcessing and Fuel Facilities), that considerably reduces the effort required to make the variance and covariance calculations needed to determine the detection sensitivity of a materials accounting system. PROFF asks questions of the user to establish the form of each term in the materials balance equation, possible correlations between them, and whether the measured quantities are characterized by an additive or multiplicative error model. Then for each term of the materials balance equation, it presents the user with a menu that is to be completed with values of the SNM concentration, mass (or volume), measurement error standard deviations, and the number of measurements made during the accounting period. On completion of all the data menus, PROFF presents the variance of the materials balance and the square root of this variance, so that the sensitivity of the accounting system can be determined. PROFF is programmed in TURBO-PASCAL for micro-computers using MS-DOS 2.1 (IBM and compatibles)

  13. Methods of Verification, Accountability and Control of Special Nuclear Material

    Energy Technology Data Exchange (ETDEWEB)

    Stewart, J.E.

    1999-05-03

    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.

  14. Nuclear material accountancy and control system in Brazil

    International Nuclear Information System (INIS)

    Full text: The Safeguards and Physical Protection Coordination (COSAP) integrates the structure of the Brazilian Nuclear Energy Commission (CNEN) that is a governmental entity in Brazil. COSAP itself is responsible for the control of nuclear materials, the physical protection of facilities handling nuclear or radioactive materials and the control of the illicit traffic of nuclear and radioactive materials. Besides this control of the nuclear material implemented by the state safeguards system, all the nuclear material after the starting point of application of safeguards is subject to a regional safeguards system (implemented by ABACC - Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials) and an international safeguards system (implemented by IAEA - International Atomic Energy Agency). Under this scope, COSAP has to maintain the inventory knowledge of nuclear material of all nuclear facilities in the country updated, and to report inventory changes to ABACC and IAEA based on data collected from the operators of the facilities. Nowadays, this data collection is made by means of collections of MS-Excel spreadsheets for support documents, general ledgers and inventory lists which is not the best situation. The accounting reports are then prepared and submitted by encrypted e-mail to ABACC and IAEA. COSAP has recently been involved in upgrading the Nuclear Material Accountancy and Control System of Brazil. Such upgrading is based on an entirely new software system (E-GAMMA) that is being developed right now in Brazil by CNEN staff. This software will be a Web system installed in a dedicated server under a secure environment maintained at CNEN headquarters, and each facility or institution will be provided with the necessary hardware and software to access the system (Digital Clients Certificates, Smart Cards, VPN, computers, etc). Users will access the system with strong passwords with creation rules and expiration dates controlled by the

  15. Survey procedure: Control and accountability of nuclear materials

    International Nuclear Information System (INIS)

    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

  16. Some technical aspects of the nuclear material accounting and control at nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    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

  18. 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).

  19. ABACC's nuclear accounting area

    International Nuclear Information System (INIS)

    The functions and activities of the Brazilian-Argentine Agency for the Accounting and Control of Nuclear Materials (ABACC) accounting area is outlined together with a detailed description of the nuclear accounting system used by the bilateral organization

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

    International Nuclear Information System (INIS)

    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

  1. Prescriptive concepts for advanced nuclear materials control and accountability systems

    International Nuclear Information System (INIS)

    Networking- and distributed-processing hardware and software have the potential of greatly enhancing nuclear materials control and accountability (MC and A) systems, from both safeguards and process operations perspectives, while allowing timely integrated safeguards activities and enhanced computer security at reasonable cost. A hierarchical distributed system is proposed consisting of groups of terminal and instruments in plant production and support areas connected to microprocessors that are connected to either larger microprocessors or minicomputers. These micros and/or minis are connected to a main machine, which might be either a mainframe or a super minicomputer. Data acquisition, preliminary input data validation, and transaction processing occur at the lowest level. Transaction buffering, resource sharing, and selected data processing occur at the intermediate level. The host computer maintains overall control of the data base and provides routine safeguards and security reporting and special safeguards analyses. The research described outlines the distribution of MC and A system requirements in the hierarchical system and distributed processing applied to MC and A. Implications of integrated safeguards and computer security concepts for the distributed system design are discussed. 10 refs., 4 figs

  2. Safeguarding nuclear materials in the former Soviet Republics through computerized materials protection, control and accountability

    International Nuclear Information System (INIS)

    The threat of nuclear weapons proliferation is a problem of global concern. International efforts at nonproliferation focus on preventing acquisition of weapons-grade nuclear materials by unauthorized states, organizations, or individuals. Nonproliferation can best be accomplished through international cooperation in the application of advanced science and technology to the management and control of nuclear materials. Computerized systems for nuclear material protection, control, and accountability (MPC and A) are a vital component of integrated nuclear safeguards programs. This paper describes the progress of scientists in the United States and former Soviet Republics in creating customized, computerized MPC and A systems. The authors discuss implementation of the Core Material Accountability System (CoreMAS), which was developed at Los Alamos National Laboratory by the US Department of Energy and incorporates, in condensed and integrated form, the most valuable experience gained by US nuclear enterprises in accounting for and controlling nuclear materials. The CoreMAS approach and corresponding software package have been made available to sites internationally. CoreMAS provides methods to evaluate their existing systems and to examine advantages and disadvantages of customizing CoreMAS or improving their own existing systems. The sites can also address crucial issues of software assurance, data security, and system performance; compare operational experiences at sites with functioning computerized systems; and reasonably evaluate future efforts. The goal of the CoreMAS project is to introduce facilities at sites all over the world to modern international MPC and A practices and to help them implement effective, modern, computerized MPC and A systems to account for their nuclear materials, and thus reduce the likelihood of theft or diversion. Sites are assisted with MPC and A concepts and the implementation of an effective computerized MPC and A system

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

    International Nuclear Information System (INIS)

    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)

  4. Role of Nuclear Material Accounting and Control System for Ensuring Nuclear Security

    International Nuclear Information System (INIS)

    The problem of nuclear material accounting and control (NMAC) already arose at the initial stage of industrial production and utilization of nuclear materials (NM) whose cost is very high and which are potentially dangerous for human health and life. The unified methodological approach at the international level to creation of NM accounting and control systems was developed in the IAEA late in seventies of the last century during design and implementation of the IAEA safeguards system, required by the Non-Proliferation Treaty (NPT). This approach was fixed, first of all, in the model agreement for application of safeguards in accordance with NPT (INFCIRC/153 corrected), and in the “Guidelines for States’ Systems of Accounting for and Control of Nuclear Material”. In these documents, requirements were established for NMAC structure, including requirements for organization of material balance areas (MBAs) and for the system of records and reports. At that time in the IAEA, quantity (NM significant quantities) and timeliness (time of detecting NM diversion) criteria of achieving the IAEA inspections goals in IAEA safeguards application were accepted. In some sense these criteria were target parameters for effective functioning of NMAC system. Created in many IAEA member states for safeguards purposes, systems of accounting and control of NM solve successfully problems not only in the safeguards area, but also in other areas where information about NM quantity, quality and location is required. Recent IAEA recommendations concerning NMAC systems are presented in the guidebook “Nuclear Material Accounting Handbook” stated from the viewpoint of IAEA safeguards application

  5. The Status of Development on a Web-Based Nuclear Material Accounting System at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byungdoo; Kim, Inchul; Lee, Seungho; Kim, Hyunjo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    The Integrated Safeguards (IS) has been applied to 10 nuclear facilities and 1 location outside facility (LOF) at the Korea Atomic Energy Research Institute (KAERI) since July 2008. One of the major changes in the implementation of safeguards under the IS is to apply the concept of a Random Interim Inspection (RII) instead of an interim inspection. The RII plan is notified within a few hours under the IS. It is thus difficult for facility operators to prepare the inspection documents within a short time if they do not periodically manage and process the nuclear material accounting data at each facility. To resolve these issues, KAERI developed a Web-based accounting system with the function of a near real-time accounting (NRTA) system to effectively and efficiently manage the nuclear material accounting data produced at the nuclear facilities and cope with a short notice inspection under the IS, called KASIS (KAeri Safeguards Information treatment System). The facility operators must input the accounting data on the inventory changes, which are the transfers of nuclear materials among the nuclear facilities and the chemical/physical composition changes, into the KASIS. KAERI also established an RFID system for controlling and managing the transfer of nuclear material and/or radioactive materials between the nuclear facilities for the purpose of nuclear safety management, and developed the nuclear material accounting system with the functions of inventory management of nuclear material at the facility level.

  6. The Status of Development on a Web-Based Nuclear Material Accounting System at KAERI

    International Nuclear Information System (INIS)

    The Integrated Safeguards (IS) has been applied to 10 nuclear facilities and 1 location outside facility (LOF) at the Korea Atomic Energy Research Institute (KAERI) since July 2008. One of the major changes in the implementation of safeguards under the IS is to apply the concept of a Random Interim Inspection (RII) instead of an interim inspection. The RII plan is notified within a few hours under the IS. It is thus difficult for facility operators to prepare the inspection documents within a short time if they do not periodically manage and process the nuclear material accounting data at each facility. To resolve these issues, KAERI developed a Web-based accounting system with the function of a near real-time accounting (NRTA) system to effectively and efficiently manage the nuclear material accounting data produced at the nuclear facilities and cope with a short notice inspection under the IS, called KASIS (KAeri Safeguards Information treatment System). The facility operators must input the accounting data on the inventory changes, which are the transfers of nuclear materials among the nuclear facilities and the chemical/physical composition changes, into the KASIS. KAERI also established an RFID system for controlling and managing the transfer of nuclear material and/or radioactive materials between the nuclear facilities for the purpose of nuclear safety management, and developed the nuclear material accounting system with the functions of inventory management of nuclear material at the facility level

  7. Annual Report ABACC 2003 - Brazilian-Argentine Agency for the Accounting and Control of Nuclear Materials

    International Nuclear Information System (INIS)

    This Report describes the actions of the Brazil-Argentine of Accounting and Control of Nuclear Materials (ABACC), during the year of 2003. The developed work allowed to concluded that there is no event indicating that any nuclear material non-accounted for were deviated for non permitted activities by the Agreement for Peaceful Use of Nuclear Energy between Argentine and Brazil and by the Four Parties Agreement among these countries, the ABACC and the International Atomic Energy Agency (IAEA)

  8. Resolution 62/96 Regulation for the accounting and control of the nuclear materials

    International Nuclear Information System (INIS)

    The present Regulation is a complementary disposition of the ordinance number 208 of May 24 National System of Accounting and Control of Nuclear Materials and it has as objective to establish the relative norms to this System. As for the responsibilities it establish that the National Center of Nuclear Security (CNSN) it is the responsible for the execution from the relative tasks to the National System of Accounting and Control of Nuclear Materials. It establishes the regulations for the following aspects: licenses and authorizations for the transportation of the nuclear material and important components, Of the ceasing of the Accounting and Control, Of the Accounting and Control of the Nuclear Materials, Control of the Important Components, The Inspections, International Organism of the Atomic Energy Safeguards

  9. Manual of use and accounting of radioactive material and procedures of radiological protection for nuclear medicine

    International Nuclear Information System (INIS)

    This manual of use and accounting of material radioactive and procedures of radiological safety tries to facilitate workings of protection of material radioactive in services of medicine nuclear, during diagnosis (examinations with x-rays, or those that are made in nuclear medicine), or during the processing of diseases, mainly of the carcinomas (x-ray)

  10. Decree 2805 by means of which the National Accounting and Control of Basic Nuclear Materials and Special Fusionable Materials System, is established

    International Nuclear Information System (INIS)

    This Decree has for object to establish a National Accounting and Control of Basic Nuclear Materials and Special Fusionable Materials System, under the supervision of the National Council for the Nuclear Industry Development. Its aims are to account nuclear materials, to control nuclear activities, to preserve and control nuclear information, to keep technical relationship with specialized organizations, and to garant nuclear safeguards

  11. Annual Report 2007 - ABACC - Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials

    International Nuclear Information System (INIS)

    This document reports activities during the year 2007 related to: technical activities as application of safeguards; management of the Quadripartite Agreement and the SCCC - Common System for Accounting and Control of Nuclear Materials; training; technical cooperation; outlook for 2008 and; institutional, administrative and financial activities; technical glossary; list of brazilian facilities; list of argentine facilities and a list of institution of nuclear area

  12. Annual report - ABACC (accounting and nuclear materials control Brazil-Argentina agency) - 1998

    International Nuclear Information System (INIS)

    The annual activities report of 1998 of accounting and nuclear materials control Brazil-Argentina agency introduces the next main topics: institutional activities - safeguards agreements implementation and administration; technical activities - planning and evaluation, operation, technical support, information accounting and treatment, technical cooperation, technical capacity invigoration; administrative and financial activities

  13. The first stage of BFS integrated system for nuclear materials control and accounting. Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-09-01

    The BFS computerized accounting system is a network-based one. It runs in a client/server mode. The equipment used in the system includes a computer network consisting of: One server computer system, including peripheral hardware and three client computer systems. The server is located near the control room of the BFS-2 facility outside of the `stone sack` to ensure access during operation of the critical assemblies. Two of the client computer systems are located near the assembly tables of the BFS-1 and BFS-2 facilities while the third one being the Fissile Material Storage. This final report details the following topics: Computerized nuclear material accounting methods; The portal monitoring system; Test and evaluation of item control technology; Test and evaluation of radiation based nuclear material measurement equipment; and The integrated demonstration of nuclear material control and accounting methods.

  14. Proceedings of the Tripartite Seminar on Nuclear Material Accounting and Control at Radiochemical Plants

    International Nuclear Information System (INIS)

    The problems of creation and operation of nuclear materials (NM) control and accounting systems and their components at radiochemical plants were discussed in seminar during November 2-6 of 1998. There were 63 Russian and 25 foreign participants in seminar. The seminar programme includes following sessions and articles: the aspects of State NM control and accountancy; NM control and accounting in radiochemical plants and at separate stages of reprocessing of spent nuclear fuel and irradiated fuel elements of commercial reactors; NM control and accountancy in storage facilities of radiochemical plants; NM control and accounting computerization, material balance assessment, preparation of reports; qualitative and quantitative measurements in NM control and accounting at radiochemical plants destructive analysis techniques

  15. 10 CFR 74.33 - Nuclear material control and accounting for uranium enrichment facilities authorized to produce...

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Nuclear material control and accounting for uranium enrichment facilities authorized to produce special nuclear material of low strategic significance. 74.33 Section 74.33 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF...

  16. Development of a computerized nuclear materials control and accounting system for a fuel reprocessing plant

    International Nuclear Information System (INIS)

    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

  17. Regional training course on state systems of accounting for and control of nuclear material

    International Nuclear Information System (INIS)

    The publication is an outline of the subjects that are included in a regional training course organized in Buenos Aires (Argentina) by the IAEA with the cooperation of the Argentine Government and the Brazilian-Argentine Agency for the Accounting and Control of Nuclear Materials (ABACC) from September 24 to October 5, 2001

  18. Production of an English/Russian glossary of terminology for nuclear materials control and accounting

    Energy Technology Data Exchange (ETDEWEB)

    Schachowskoj, S.; Smith, H.A. Jr.

    1995-05-01

    The program plans for Former Soviet Union National Nuclear Materials Control and Accounting (MC and A) Systems Enhancements call for the development of an English/Russian Glossary of MC and A terminology. This glossary was envisioned as an outgrowth of the many interactions, training sessions, and other talking and writing exercises that would transpire in the course of carrying out these programs. This report summarizes the status of the production of this glossary, the most recent copy of which is attached to this report. The glossary contains over 950 terms and acronyms associated with nuclear material control and accounting for safeguards and nonproliferation. This document is organized as follows: English/Russian glossary of terms and acronyms; Russian/English glossary of terms and acronyms; English/Russian glossary of acronyms; and Russian/English glossary of acronyms.

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

    International Nuclear Information System (INIS)

    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.)

  20. Production of an English/Russian glossary of terminology for nuclear materials control and accounting

    International Nuclear Information System (INIS)

    The program plans for Former Soviet Union National Nuclear Materials Control and Accounting (MC and A) Systems Enhancements call for the development of an English/Russian Glossary of MC and A terminology. This glossary was envisioned as an outgrowth of the many interactions, training sessions, and other talking and writing exercises that would transpire in the course of carrying out these programs. This report summarizes the status of the production of this glossary, the most recent copy of which is attached to this report. The glossary contains over 950 terms and acronyms associated with nuclear material control and accounting for safeguards and nonproliferation. This document is organized as follows: English/Russian glossary of terms and acronyms; Russian/English glossary of terms and acronyms; English/Russian glossary of acronyms; and Russian/English glossary of acronyms

  1. Advanced international training course on state systems of accounting for and control of nuclear materials

    International Nuclear Information System (INIS)

    This report incorporates all lectures and presentations at the Advanced International Training Course on State Systems of Accounting for and Control of Nuclear Material held April 27 through May 12, 1981 at Santa Fe and Los Alamos, New Mexico, and Richland, Washington, USA. Authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, the course was developed to provide practical training in the design, implementation, and operation of a state system of nuclear materials accountability and control that satisfies both national and international safeguards. Major emphasis for the 1981 course was placed on safeguards methods used at bulk-handling facilities, particularly low-enriched uranium conversion and fuel fabrication plants. The course was conducted by the University of California's Los Alamos National Laboratory, the Battelle Pacific Northwest Laboratory, and Exxon Nuclear Company, Inc. Tours and demonstrations were arranged at both the Los Alamos National Laboratory, Los Alamos, New Mexico, and the Exxon Nuclear fuel fabrication plant, Richland, Washington

  2. Advanced international training course on state systems of accounting for and control of nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    1981-10-01

    This report incorporates all lectures and presentations at the Advanced International Training Course on State Systems of Accounting for and Control of Nuclear Material held April 27 through May 12, 1981 at Santa Fe and Los Alamos, New Mexico, and Richland, Washington, USA. Authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, the course was developed to provide practical training in the design, implementation, and operation of a state system of nuclear materials accountability and control that satisfies both national and international safeguards. Major emphasis for the 1981 course was placed on safeguards methods used at bulk-handling facilities, particularly low-enriched uranium conversion and fuel fabrication plants. The course was conducted by the University of California's Los Alamos National Laboratory, the Battelle Pacific Northwest Laboratory, and Exxon Nuclear Company, Inc. Tours and demonstrations were arranged at both the Los Alamos National Laboratory, Los Alamos, New Mexico, and the Exxon Nuclear fuel fabrication plant, Richland, Washington.

  3. A role for distributed processing in advanced nuclear materials control and accountability systems

    International Nuclear Information System (INIS)

    Networking and distributed processing hardware and software have the potential of greatly enhancing nuclear materials control and account-ability (MCandA) systems, both from safeguards and process operations perspectives while allowing timely integrated safeguards activities and enhanced computer security at reasonable cost. A hierarchical distributed system is proposed consisting of groups of terminals and instruments in plant production and support areas connected to microprocessors that are connected to either larger microprocessors or minicomputers. The structuring and development of a limited distributed MCandA prototype system, including human engineering concepts, are described. Implications of integrated safeguards and computer security concepts to the distributed system design are discussed

  4. Using the general principles of quality assessment of the facilities while examining the nuclear materials accounting and control system at enterprises

    International Nuclear Information System (INIS)

    The issue of control and regulation in the field of adequate accounting and control of nuclear material is discussed. Ways of improving the nuclear materials accounting and control system at nuclear facilities in the Russian Federation are presented

  5. Current status of the system of accounting for and control of nuclear materials in the Philippines

    International Nuclear Information System (INIS)

    as environmental sampling to our isotope laboratories. Technical assistance in the establishment of computerized system of nuclear materials accounting and control was solicited from the IAEA in 1985. The computer utilized the VAX11/750. At present, the data were in text file, which we hope to send by electronic mail. (author)

  6. Training and Professional Development of Specialists in Nuclear Materials Physical Protection, Accounting and Control in Ukraine

    International Nuclear Information System (INIS)

    In the core of the national policy of Ukraine governing physical protection of nuclear facilities, nuclear material, radioactive wastes and other sources of ionizing radiation lie the recognition that activity carried out by individuals in area of regulation and implementation of physical protection measures is a profession in the domain of nuclear energy use and radiation safety, as well as the need to create a state system for professional training, retraining and skill improvement of physical protection personnel.1. The Ukrainian Ministry of Energy and Coal Industry as a central executive authority responsible for physical protection of nuclear installations, nuclear material, radioactive wastes and other sources of ionizing radiation at facilities in the Ministry’s jurisdiction sees professional training and development of physical protection specialists as a key factor in strengthening the nuclear non-proliferation regime. Based on the understanding that a specialist is an individual having a specialty, highly qualified, profoundly knowledgeable in a certain scientific or technical discipline, and demonstrating skill in both the basics and in-depth aspects of their profession, the Ministry listed goals and responsibilities of specialists and requirements to their knowledge, skill, and professional experience in 2008. Also in 2009, jointly with the concerned authorities the Ministry developed requirements to the physical protection department and personnel. Accordingly, the main task is to provide the fuel and energy sector of Ukraine with experts and high-level professionals, those who are experts in their field, are highly qualified and profoundly knowledgeable in the field of physical protection, control and accounting of nuclear materials

  7. Game theory and decision support system for use in security reviews of nuclear material tracking and accountancy systems

    International Nuclear Information System (INIS)

    Tracking and accountancy arrangements help guarantee the security of nuclear materials. Verifications consisting of comparisons between physical identifications or measurements on one hand and material accountancy on the other hand are carried out, in order to detect any unexpected absence of nuclear material. This paper studies two different aspects of the problem of the efficiency of these verifications. First, a decision support system for use in security reviews of nuclear material accountancy systems is presented. Its purpose is firstly to represent a facility and the associated verifications, tracking and accountancy operations and secondly, to calculate the detection delay in the case of an absence of nuclear material. Next, in order to minimize the detection delay for a limited, fixed number of physical identifications, a two-person, zero-sum game with incomplete information is described. The first results obtained from this analysis indicate shorter detection times than those given by games with complete information

  8. Detecting anomalous nuclear materials accounting transactions: Applying machine learning to plutonium processing facilities

    International Nuclear Information System (INIS)

    Nuclear materials accountancy is the only safeguards measure that provides direct evidence of the status of nuclear materials. Of the six categories that gives rise to inventory differences, the technical capability is now in place to implement the technical innovations necessary to reduce the human error categories. There are really three main approaches to detecting anomalies in materials control and accountability (MC ampersand A) data: (1) Statistical: numeric methods such as the Page's Test, CUSUM, CUMUF, SITMUF, etc., can detect anomalies in metric (numeric) data. (2) Expert systems: Human expert's rules can be encoded into software systems such as ART, KEE, or Prolog. (3) Machine learning: Training data, such as historical MC ampersand A records, can be fed to a classifier program or neutral net or other machine learning algorithm. The Wisdom ampersand Sense (W ampersand S) software is a combination of approaches 2 and 3. The W ampersand S program includes full features for adding administrative rules and expert judgment rules to the rule base. if desired, the software can enforce consistency among all rules in the rule base

  9. Assistance to newly independent states in establishing state systems of accounting and control of nuclear material

    International Nuclear Information System (INIS)

    Nuclear trade and co-operation among States are essential dependent upon effective and credible safeguards. The disintegration of the former Soviet Union has resulted, inter alia, in the emergence of a number of newly independent States (NIS). With one exception, all the NIS have declared their intention either to become or to remain non-nuclear-weapon States, but many of them have nuclear programmes. However, the nuclear infrastructure on which those programmes once rested is no longer in place and needs to be reconstructed. The paper outlines work under way among the IAEA, its Member States and the NIS relating to the establishment and development in the NIS of State Systems of Accounting and Control (SSAC) of nuclear material. The paper describes IAEA activities in the NIS, including fact-finding missions and technical visits, the successful attempts to find donor States providing voluntary funding and expertise, and the co-ordination of technical support between the IAEA and the donor States. (author). 3 tabs

  10. Basic concepts of materials accounting

    International Nuclear Information System (INIS)

    The importance of accounting for nuclear materials to the efficient, safe, and economical operation of nuclear facilities is introduced, and the following topics are covered: material balance equation; item control areas; material balance uncertainty; decision procedures for materials accounting; conventional and near-real-time accounting; regulatory requirements of the US Department of Energy and the Nuclear Regulatory Commission; and a summary related to the development of a materials accounting system to implement the basic concepts described. The summary includes a section on each of the following: problem definition, system objectives, and system design

  11. Nuclear fuel lease accounting

    International Nuclear Information System (INIS)

    The subject of nuclear fuel lease accounting is a controversial one that has received much attention over the years. This has occurred during a period when increasing numbers of utilities, seeking alternatives to traditional financing methods, have turned to leasing their nuclear fuel inventories. The purpose of this paper is to examine the current accounting treatment of nuclear fuel leases as prescribed by the Financial Accounting Standards Board (FASB) and the Federal Energy Regulatory Commission's (FERC's) Uniform System of Accounts. Cost accounting for leased nuclear fuel during the fuel cycle is also discussed

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

    International Nuclear Information System (INIS)

    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

  13. Evaluating Safeguards Benefits of Process Monitoring as compared with Nuclear Material Accountancy

    Energy Technology Data Exchange (ETDEWEB)

    Humberto Garcia; Wen-Chiao Lin; Reed Carlson

    2014-07-01

    This paper illustrates potential safeguards benefits that process monitoring (PM) may have as a diversion deterrent and as a complementary safeguards measure to nuclear material accountancy (NMA). This benefit is illustrated by quantifying the standard deviation associated with detecting a considered material diversion scenario using either an NMA-based method or a PM-based approach. To illustrate the benefits of PM for effective safeguards, we consider a reprocessing facility. We assume that the diversion of interest for detection manifests itself as a loss of Pu caused by abnormally operating a dissolver for an extended period to accomplish protracted diversion (or misdirection) of Pu to a retained (unconditioned) waste stream. For detecting the occurrence of this diversion (which involves anomalous operation of the dissolver), we consider two different data evaluation and integration (DEI) approaches, one based on NMA and the other based on PM. The approach based on PM does not directly do mass balance calculations, but rather monitors for the possible occurrence of anomaly patterns related to potential loss of nuclear material. It is thus assumed that the loss of a given mass amount of nuclear material can be directly associated with the execution of proliferation-driven activities that trigger the occurrence of an anomaly pattern consisting of series of events or signatures occurring at different unit operations and time instances. By effectively assessing these events over time and space, the PM-based DEI approach tries to infer whether this specific pattern of events has occurred and how many times within a given time period. To evaluate the goodness of PM, the 3 Sigma of the estimated mass loss is computed under both DEI approaches as function of the number of input batches processed. Simulation results are discussed.

  14. 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

  15. Decree of the Czechoslovak Atomic Energy Commission No. 28/1977 on the accountancy and inspection of nuclear materials

    International Nuclear Information System (INIS)

    The Decree specifies regulatory requirements placed on the accountancy and inspection of nuclear materials and commitments following from the Nuclear Weapons Non-Proliferation Treaty. The responsibilities of state surveillance inspectors are laid down, as are the obligations of organizations to keep records and take stock of nuclear materials and to report on this to the Czechoslovak Atomic Energy Agency. The responsibilities associated with nuclear materials exports and imports are also specified. The Decree entered into force on 1 June 1977. (J.B.)

  16. The Russian Federal Information System for Nuclear Material Control and Accounting: Yesterday, Today and Tomorrow

    International Nuclear Information System (INIS)

    Most enterprises in the Russian Federation are not prepared to report to the Russian Federal Nuclear Material Control and Accounting Information System (FIS) by the full function reporting method. The full function reporting method requires reporting inventory listings on a schedule based on nuclear material category, submission of individual inventory change reports, and reconciliation and closeout at the end of each reporting period. Most Russian enterprises do not have automated systems and do not have the resources to develop and implement such systems. Over the last two years, MinAtom put the regulations and national level nuclear material control and accounting (MC and A) software in place to require all enterprises in the Russian Federation to report summarized inventory listings to the FIS in January 2002. Enterprises do not need automated systems to comply with summarized reporting requirements. Along with the approximately 25% of the total Category 1 Material Balance Areas (MBAs) using full function reporting, the addition of this complete summarized inventory makes the FIS a more valuable tool for MinAtom management. The FIS is now poised to complete the work by improving the integrity and reliability of the data through increasing the number of enterprises and MBAs using full function reporting. There are obstacles and issues that must be dealt with along the way to achieving the final goal of every MBA sending inventory and inventory change reports using the full function reporting method. Summarized reporting is a major step toward this final goal. Currently all MBAs using full function reporting are doing so under a U.S. contract. FIS management recognized full function reporting could not be implemented in the near-term and prepared a plan with immediate, intermediate, and long-term FIS tasks. To address the major obstacles and optimize implementation, two paths need to be followed in parallel: developing the regulatory basis and overcoming

  17. Nuclear Material Accountability Applications of a Continuous Energy and Direction Gamma Ray Detector

    Energy Technology Data Exchange (ETDEWEB)

    David Gerts; Robert Bean; Marc Paff

    2010-07-01

    The Idaho National Laboratory has recently developed a detector system based on the principle of a Wilson cloud chamber that gives the original energy and direction to a gamma ray source. This detector has the properties that the energy resolution is continuous and the direction to the source can be resolved to desired fidelity. Furthermore, the detector has low power requirements, is durable, operates in widely varying environments, and is relatively cheap to produce. This detector is expected, however, to require significant time to perform measurements. To mitigate the significant time for measurements, the detector is expected to scale to very large sizes with a linear increase in cost. For example, the proof of principle detector is approximately 30,000 cm3. This work describes the technical results that lead to these assertions. Finally, the applications of this detector are described in the context of nuclear material accountability.

  18. A Continuous Automated Vault Inventory System (CAVIS) for accountability monitoring of stored nuclear materials

    International Nuclear Information System (INIS)

    Nearly all facilities that store hazardous (radioactive or non-radioactive) materials must comply with prevailing federal, state, and local laws. These laws usually have components that require periodic physical inspections to insure that all materials remain safely and securely stored. The inspections are generally labor intensive, slow, put personnel at risk, and only find anomalies after they have occurred. The system described in this paper was developed for monitoring stored nuclear materials resulting from weapons dismantlement, but its applications extend to any storage facility that meets the above criteria. The traditional special nuclear material (SNM) accountability programs, that are currently used within most of the Department of Energy (DOE) complex, require the physical entry of highly trained personnel into SNM storage vaults. This imposes the need for additional security measures, which typically mandate that extra security personnel be present while SNM inventories are performed. These requirements increase labor costs and put additional personnel at risk to radiation exposure. In some cases, individuals have received radiation exposure equivalent to the annual maximum during just one inventory verification. With increasing overhead costs, the current system is rapidly becoming too expensive to operate, the need for an automated method of inventory verification is evident. The Continuous Automated Vault Inventory System (CAVIS) described in this paper was designed and prototyped as a low cost, highly reliable, and user friendly system that is capable of providing, real-time weight, gamma. and neutron energy confirmation from each item stored in a SNM vault. This paper describes the sensor technologies, the CAVIS prototype system (built at Y- 12 for highly enriched uranium storage), the technical requirements that must be achieved to assure successful implementation, and descriptions of sensor technologies needed for a plutonium facility

  19. Nuclear materials control and accountability (NMC and A) auditors in the 90's

    International Nuclear Information System (INIS)

    The increase in emphasis on the adequacy of the NMC and A internal control systems requires that management define what type of training and experience is needed by NMC and A Internal Audit Program. At Martin Marietta Energy Systems, inc. (the prime contractor for the Department of Energy at Oak Ridge, Tenn.), the Central NMC and A Manager has developed a comprehensive set of NMC and A Internal Audit policies that defines performance standards, methods of conducting audits, mechanisms for ensuring appropriate independence for NMC and A auditors, structure for standardized audit reports and working papers, and a section that addresses the development of training plans for individual NMC and A auditors. The training requirements reflect the unique combination of skills necessary to be an effective NMC and A Internal Auditor- a combination of the operational auditing skills of a Certified Internal Auditor, the accounting auditing capabilities of a Certified Public Accountant, and the specific technical knowledge base associated with nuclear materials. This paper presents a mechanism for identifying an individual training program for NMC and A auditors that considers the above requirements and the individual's long-range career goals

  20. Procedures and practices in nuclear material accounting and reporting in the GDR

    International Nuclear Information System (INIS)

    The typical features of the GDR's nuclear material safeguards system are pointed out by analysing the nuclear material data reporting to the IAEA since 1972. Extent and consequences of the application of modern electronic data registration and processing methods at State and MBA levels are considered and an outlook is given for planned developments and extensions of the data processing system with a view to making the data exchange between the main users of nuclear material and the State control authority more effective and the work of the State control authority itself more efficient

  1. Application of game theory to nuclear material accounting. Final report, 1 April 1977-3 January 1978

    International Nuclear Information System (INIS)

    An approach based upon the theory of games is presented that determines an optimal alarm threshold for detecting unauthorized or deliberate diversion of nuclear material based upon material accounting data. A mathematical model is developed, solved, and applied to a generic nuclear facility. By considering a malevolent diverter as a basic ingredient of the analysis, this approach offers advantages over conventional statistical hypothesis testing. The results show that periodic inventories and appropriate interpretation of MUF (Material Unaccounted For) can provide a high assurance for indicating diversion in a nuclear material safeguards situation. The optimal policy is to select the alarm threshold by a mixed strategy rather than a pre-set single fixed value. Procedures for doing this are presented in the report. With this approach, MUF data by itself may be more useful in indicating possible unauthorized diversion of special nuclear material

  2. Current status of the system of accounting for and control of nuclear materials in the Philippines

    International Nuclear Information System (INIS)

    Prior to the construction of nuclear power plant in 1976, the only safeguarded nuclear materials in the Philippines were the nuclear fuels of the research reactor (PRR-1). The arrival of the nuclear fuels of the Bataan Nuclear Power Plant (BNPP) in 1984 increased the number of safeguarded nuclear materials. Further, the upgrading of the present MTR reactor to a TRIGA type in 1987 necessitated the acquisition of additional nuclear fuels. With the decision of the Philippine Government to mothball the BNPP in 1986, the operator, the National Power Corporation, made arrangements to sell the nuclear fuel assemblies. In December 1997 Siemens Power Corporation bought the fresh fuel assemblies. On the other hand, the spent fuel assemblies of mixed enrichment from PRR-1 were shipped to the United States on 14 March 1999. This shipment was in line with the U.S. initiative to implement its Record of Decision to accept and manage all foreign research reactors uranium fuels of U.S. origin. The only safeguarded materials left are the TRIGA fuels and the complete reactor assembly of BNPP. (author)

  3. ABACC - Brazil-Argentina Agency for Accounting and Control of Nuclear Materials, a model of integration and transparence

    International Nuclear Information System (INIS)

    Argentina and Brazil began its activities in the nuclear area about the same time, in the 50 century past. The existence of an international nuclear nonproliferation treaty-TNP-seen by Brazil and Argentina as discriminatory and prejudicial to the interests of the countries without nuclear weapons, led to the need for a common system of control of nuclear material between the two countries to somehow provide assurances to the international community of the exclusively peaceful purpose of its nuclear programs. The creation of a common system, assured the establishment of uniform procedures to implement safeguards in Argentina and Brazil, so the same requirements and safeguards procedures took effect in both countries, and the operators of nuclear facilities began to follow the same rules of control of nuclear materials and subjected to the same type of verification and control. On July 18, 1991, the Bilateral Agreement for the Exclusively Peaceful Use of Nuclear Energy created a binational body, the Argentina-Brazil Agency for Accounting and Control of Nuclear Materials-ABACC-to implement the so-called Common System of Accounting and Control of Nuclear materials - SCCC. The deal provided, permanently, a clear commitment to use exclusively for peaceful purposes all material and nuclear facilities under the jurisdiction or control of the two countries. The Quadripartite Agreement, signed in December of that year, between the two countries, ABACC and IAEA completed the legal framework for the implementation of comprehensive safeguards system. The 'model ABACC' now represents a paradigmatic framework in the long process of economic, political, technological and cultural integration of the two countries. Argentina and Brazil were able to establish a guarantee system that is unique in the world today and that consolidated and matured over more than twenty years, has earned the respect of the international community

  4. Protection, control, accounting and disposition of nuclear-explosive materials: Recent developments in the United States and Russia

    International Nuclear Information System (INIS)

    In the frame of recent development in the USA and Russia concerning protection, control, accounting and disposition of nuclear-explosive materials, the paper presents in detail the status of US-Russian agreement on fissile materials, namely deactivation and dismantling; transparency; removal of material from possibility of military use; safe and secure storage; production cut-off. Findings of the Center for International Security and Arms Control (CISAC) Panel on reactor related options for disposition of excess weapon plutonium are included

  5. Experience gained with nuclear material accounting and control in storage facility for plutonium dioxide of SChK radiochemical plant

    International Nuclear Information System (INIS)

    The task for the computerized accounting of containers at the storage with barcoding equipment for inventory taking has been performed at achieve the pre-commissioning phase. This gave the following upgrade: decrease of the time spent by the personnel in storage compartments with plutonium dioxide during inventory taking, this diminishing the dose for personnel; changeover from traditional record book to computerized accounting of nuclear materials at the storage, which will make it possible to include the local workstation of the storage into computer network for nuclear material (NM) accounting at the Radiochemical plant; test and improve technique for the use of barcoding equipment for further introduction at plants and storage facilities of the SChK. Works are underway for further improvement of the NM accounting at the storage for plutonium dioxide

  6. Development of technologies for national control of and accountancy for nuclear materials

    International Nuclear Information System (INIS)

    The aim of this project is to establish a rigid foundation of national safeguards and to develop the new technologies for the nuclear control. This project is composed of four different technologies; 1. Monitoring technology for nuclear materials, 2. Detection technology for a single particle, 3. Safeguards information management technology, 4. Physical protection technology. Various studies such as a remote verification system for CANDU spent fuel in dry storage canister, a spent fuel verification system using an optical fiber scintillator, and development of softwares for safeguards and physical protection were performed in the frist phase('99-'01). As a result of this research, it has been identified that the developed technologies could be a crucial means of the control for the nuclear material and facilities related. We are planing to accomplish a steady national safeguard system in the second phase('02-'06). This research will help to elevate the transparency and credibility in national nuclear activities by improving the relative technologies

  7. State systems of accounting for and control of nuclear materials in the Republic of Uzbekistan

    International Nuclear Information System (INIS)

    After the breakup of the USSR the Republic of Uzbekistan has been working in the following areas, attaching primary importance to producing a legislative the structure for the safe use of nuclear energy: legal framework for nuclear and radiation safety; licensing and control of nuclear facilities and radiation sources; regulations for the safe transport of nuclear and radioactive materials; emergency preparedness. Presentation includes description of principal elements and the function of the SSAC; nuclear activities in Uzbekistan (Atomic inspection safeguarded at the beginning of 2001, 9 installations, 2 Research Reactors, 2 Uranium mine and reprocessing plants, 5 Storage installations). The current Uzbekistan's SSAC has been developed and fully satisfies both the IAEA safeguards requirements. The Republic of Uzbekistan supports the introduction of the 'integrated safeguards'. There is need to further strengthen the relationship between the Uzbekistan's SSAC and the IAEA under an integrated safeguards regime to provide more effective and efficient safeguards application

  8. Nuclear fuels accounting interface: River Bend experience

    Energy Technology Data Exchange (ETDEWEB)

    Barry, J.E.

    1986-01-01

    This presentation describes nuclear fuel accounting activities from the perspective of nuclear fuels management and its interfaces. Generally, Nuclear Fuels-River Bend Nuclear Group (RBNG) is involved on a day-by-day basis with nuclear fuel materials accounting in carrying out is procurement, contract administration, processing, and inventory management duties, including those associated with its special nuclear materials (SNM)-isotopics accountability oversight responsibilities as the Central Accountability Office for the River Bend Station. As much as possible, these duties are carried out in an integrated, interdependent manner. From these primary functions devolve Nuclear Fuels interfacing activities with fuel cost and tax accounting. Noting that nuclear fuel tax accounting support is of both an esoteric and intermittent nature, Nuclear Fuels-RBNG support of developments and applications associated with nuclear fuel cost accounting is stressed in this presentation.

  9. Nuclear fuels accounting interface: River Bend experience

    International Nuclear Information System (INIS)

    This presentation describes nuclear fuel accounting activities from the perspective of nuclear fuels management and its interfaces. Generally, Nuclear Fuels-River Bend Nuclear Group (RBNG) is involved on a day-by-day basis with nuclear fuel materials accounting in carrying out is procurement, contract administration, processing, and inventory management duties, including those associated with its special nuclear materials (SNM)-isotopics accountability oversight responsibilities as the Central Accountability Office for the River Bend Station. As much as possible, these duties are carried out in an integrated, interdependent manner. From these primary functions devolve Nuclear Fuels interfacing activities with fuel cost and tax accounting. Noting that nuclear fuel tax accounting support is of both an esoteric and intermittent nature, Nuclear Fuels-RBNG support of developments and applications associated with nuclear fuel cost accounting is stressed in this presentation

  10. Nuclear material accounting reports to the IAEA: (code 10 of Subsidiary Arrangements)

    International Nuclear Information System (INIS)

    The INFCIRC/153-type safeguard agreements provide the basis to inform the IAEA on the nuclear materials in the Member States. Reports to be provided to the the Agency consist of three types: Inventory Change Report (ICR), Physical Inventory Listing (PIL) and Material Balance Report (MBR). Concise notes may be provided for any of these reports. An explanation for the use of the report forms is given

  11. Achievements, current status and prospects for Russian-American cooperation in nuclear material physical protection, control and accounting - 1998

    International Nuclear Information System (INIS)

    The process of upgrading the material physical protection, control and accounting systems is an ongoing and long-term process that consists of modernization measuring equipment and methodologies, improving, data exchange and processing technologies, and improving administrative procedures. The positive results that was already achieved form a foundation upon which this collaboration may extend into other new and important areas, such as - the second and third lines of defence, which are directed toward countering illegal trafficking not only in nuclear materials, but in other hazardous substances that constitute a threat to the nuclear sites and national security of the countries

  12. Minatom of Russia Situation and Crisis Center and the Automated Federal Information System for Nuclear Material Control and Accounting

    International Nuclear Information System (INIS)

    Under the Situation and Crisis Center (SCC) management, the Information Analytical Center (IAC) of the Ministry of Atomic Energy (Minatom) of Russia was created to oversee the operation of the Federal Nuclear Material Control and Accounting Information System (FIS). During 2000, the FIS achieved an important milestone in its development: the basic functions of the information system were implemented. This includes placing into operation the collecting and processing of nuclear material control and accounting (MC and A) information from the enterprises reporting to the FIS. The FIS began working with 14 Russian enterprises to develop and implement full-function reporting (i.e., reporting inventory and inventory changes including closeout and reconciliation between the FIS and enterprises). In 2001, the system will expand to include enterprise-level inventory information for all enterprises using nuclear materials in Russia. For this reason, at the end of 2000 through the beginning of 2001, five separate training sessions were held for over 100 enterprise personnel responsible for preparation and transfer of the reports to the FIS. Through the assistance of the Nuclear Material Protection, Control and Accounting (MPC and A) program, information systems for the accounting of nuclear materials are being installed at Russia enterprises. In creating the program for modernization of the Russian Federation State System of Accounting and Control (SSAC) of nuclear material, the SCC conducted a survey of the enterprises to determine the readiness of their internal MC and A systems for reporting to the FIS. Based on the information from the survey and the results of the projects on creation of local information systems at Russian enterprises, the analysis of information and the technical aspects of MC and A systems identified deficiencies that were analyzed and recommendations for eliminating these deficiencies were proposed. The concentration of analytical and administrative

  13. International training course on implementation of state systems of accounting for and control of nuclear materials: proceedings

    Energy Technology Data Exchange (ETDEWEB)

    1984-06-01

    This report incorporates all lectures and presentations at the International Training Course on Implementation of State Systems of Accounting for and Control of Nuclear Materials held October 17 through November 4, 1983, at Santa Fe and Los Alamos, New Mexico and Richland, Washington, USA. Authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, the course was developed to provide practical training in the design, implementation, and operation of a State system of nuclear materials accountability and control that satisfies both national and international safeguards requirements. Major emphasis for the 1983 course was placed on safeguards methods used at bulk-handling facilities, particularly low-enriched uranium conversion and fuel fabrication plants. The course was conducted by the University of California's Los Alamos National Laboratory and Exxon Nuclear Company, Inc. Tours and demonstrations were arranged at the Los Alamos National Laboratory, Los Alamos, New Mexico, and the Exxon Nuclear fuel fabrication plant, the Battelle Pacific Northwest Laboratory, Westinghouse Fast Flux Test Facility Visitor Center, and Washington Public Power System nuclear reactor facilities in Richland, Washington. Individual presentations were indexed for inclusion in the Energy Data Base.

  14. International training course on implementation of state systems of accounting for and control of nuclear materials: proceedings

    International Nuclear Information System (INIS)

    This report incorporates all lectures and presentations at the International Training Course on Implementation of State Systems of Accounting for and Control of Nuclear Materials held October 17 through November 4, 1983, at Santa Fe and Los Alamos, New Mexico and Richland, Washington, USA. Authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, the course was developed to provide practical training in the design, implementation, and operation of a State system of nuclear materials accountability and control that satisfies both national and international safeguards requirements. Major emphasis for the 1983 course was placed on safeguards methods used at bulk-handling facilities, particularly low-enriched uranium conversion and fuel fabrication plants. The course was conducted by the University of California's Los Alamos National Laboratory and Exxon Nuclear Company, Inc. Tours and demonstrations were arranged at the Los Alamos National Laboratory, Los Alamos, New Mexico, and the Exxon Nuclear fuel fabrication plant, the Battelle Pacific Northwest Laboratory, Westinghouse Fast Flux Test Facility Visitor Center, and Washington Public Power System nuclear reactor facilities in Richland, Washington. Individual presentations were indexed for inclusion in the Energy Data Base

  15. Collaborative Russian-US work in nuclear material protection, control and accounting at the Institute of Physics and Power Engineering

    International Nuclear Information System (INIS)

    The Institute of Physics and Power Engineering (IPPE) is a leading research center under the Ministry of Atomic Energy of the Russian Federation. IPPE encompasses many installations and many specialists who perform fundamental and applied investigations in nuclear power and technology for the national nuclear program. IPPE has a key role in the national nuclear material protection, control, and accounting (MPC ampersand A) system both as a nuclear facility and also as a training center for MPC ampersand A. As a participant in the US-Russian Laboratory-to-Laboratory Cooperative Program in MPC ampersand A, IPPE is conducting several tasks in collaboration with US Department of Energy national laboratories. The main goal of these tasks is the rapid improvement of MPC ampersand A at one of the most sensitive operating IPPE installations, the BFS critical facility, which has large numbers of fuel items containing highly enriched uranium and weapons-grade plutonium. After the completion of several test, evaluation, and demonstration tasks, it is hoped that the tested and adopted methods and procedures can be applied not only to the entire population of BFS fuel items, but also to other facilities at IPPE and other Russian nuclear institutes and operating facilities. The collaborative tasks cover seven areas: computerized nuclear material accounting, entry control and portals, item control and inventory, design evaluation and analysis, gamma and neutron assay, an integrated demonstration, and physical protection elements and test bed

  16. 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 (linac) 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.

  17. 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.

  18. Department of Energy Nuclear Material Protection, Control, and Accounting Program at the Mangyshlak Atomic Energy Complex, Aktau, Republic of Kazakhstan

    International Nuclear Information System (INIS)

    As part of the Cooperative Threat Reduction Nuclear Material Protection, Control, and Accounting (MPC and A) Program, the US Department of Energy and Mangyshlak Atomic Energy Complex (MAEC), Aktau, Republic of Kazakstan have cooperated to enhance existing MAEC MPC and A features at the BN-350 liquid-metal fast-breeder reactor. This paper describes the methodology of the enhancement activities and provides representative examples of the MPC and A augmentation implemented at the MAEC

  19. International training course on implementation of state systems of accounting for and control of nuclear materials: proceedings

    International Nuclear Information System (INIS)

    This report incorporates all lectures and presentations at the International Training Course on Implementation of State Systems of Accounting for and Control of Nuclear Materials held June 3 through June 21, 1985, at Santa Fe and Los Alamos, New Mexico, and San Clemente, California. Authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, the Course was developed to provide practical training in the design, implementation, and operation of a state system of nuclear materials accountability and control that satisfies both national and international safeguards requirements. Major emphasis for the 1985 course was placed on safeguards methods used at item-control facilities, particularly nuclear power generating stations and test reactors. An introduction to safeguards methods used at bulk handling facilities, particularly low-enriched uranium conversion and fuel fabrication plants, was also included. The course was conducted by the University of California's Los Alamos National Laboratory and the Southern California Edison Company. Tours and demonstrations were arranged at the Los Alamos National Laboratory, Los Alamos, New Mexico, and the San Onofre Nuclear Generating Station, San Clemente, California

  20. International training course on implementation of state systems of accounting for and control of nuclear materials: proceedings

    Energy Technology Data Exchange (ETDEWEB)

    1986-06-01

    This report incorporates all lectures and presentations at the International Training Course on Implementation of State Systems of Accounting for and Control of Nuclear Materials held June 3 through June 21, 1985, at Santa Fe and Los Alamos, New Mexico, and San Clemente, California. Authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, the Course was developed to provide practical training in the design, implementation, and operation of a state system of nuclear materials accountability and control that satisfies both national and international safeguards requirements. Major emphasis for the 1985 course was placed on safeguards methods used at item-control facilities, particularly nuclear power generating stations and test reactors. An introduction to safeguards methods used at bulk handling facilities, particularly low-enriched uranium conversion and fuel fabrication plants, was also included. The course was conducted by the University of California's Los Alamos National Laboratory and the Southern California Edison Company. Tours and demonstrations were arranged at the Los Alamos National Laboratory, Los Alamos, New Mexico, and the San Onofre Nuclear Generating Station, San Clemente, California.

  1. NDA systems to support nuclear material control and accounting in spent fuel reprocessing plants

    International Nuclear Information System (INIS)

    Detailed descriptions of a number of instrument systems relating to accountancy and safeguarding of plutonium operations and storage on Thermal Oxide Plant (Thorp) are provided. The systems described include the Plutonium Inventory Measurement System (PIMS), used to provide Near Real Time Materials Accountancy (NRTMA) information within the Thorp plutonium finishing area; the Product Can Contents Monitor (PCCM), used to verify can weight measurements and isotopic composition and; the In-Store Plutonium Verification Monitor, used to provide in-situ measurements of plutonium in cans whilst they are in their storage channels. These nondestructive systems are necessarily combined with other physical security, surveillance and identification arrangements for the handling and storage of plutonium product cans

  2. US/Russian cooperative efforts in nuclear material protection, control, and accounting at the Siberian Chemical Combine

    International Nuclear Information System (INIS)

    The Siberian Chemical Combine (SKhK) is the largest multifunction nuclear production facility in the Russian nuclear complex. Until recently, it produced and processed special nuclear material for the Russian Defense Ministry. SKhK and its US partners in the Department of Energy (DOE) US/Russian Materials Protection, Control, and Accountability (MPC and A) Program are nearing completion of the initial MPC and A upgrades at the six SKhK plant sites that were begun three years ago. Comprehensive enhancements to the physical protection and access control systems are progressing on a site-wide basis while a comprehensive MC and A system is being implemented at the Radiochemical Plant site. SKhK now produces thermal and electrical power, enriches uranium for commercial reactor fuel, reprocesses irradiated fuel, converts high-enriched uranium metal into high-enriched oxide for blending into reactor-grade, low-enriched uranium, and manufactures civilian products. The authors review the progress to date and outline plans for continuing the work in 1999

  3. Trial operation of material protection, control, and accountability systems at two active nuclear material handling sites within the All-Russian Institute of Experimental Physics (VNIIEF)

    International Nuclear Information System (INIS)

    This paper discusses Russian Federal Nuclear Center (RFNC)-VNIIEF activities in the area of nuclear material protection, control, and accounting (MPC and A) procedures enhancement. The goal of such activities is the development of an automated systems for MPC and A at two of the active VNIIEF research sites: a research (reactor) site and a nuclear material production facility. The activities for MPC and A system enhancement at both sites are performed in the framework of a VNIIEF-Los Alamos National Laboratory contract with participation from Sandia National Laboratories, Lawrence Livermore National Laboratory, Brookhaven National Laboratory, Oak Ridge National Laboratory, Pacific Northwest National Laboratory, and PANTEX Plant in accordance with Russian programs supported by MinAtom. The American specialists took part in searching for possible improvement of technical solutions, ordering equipment, and delivering and testing the equipment that was provided by the Americans

  4. Establishing a system of nuclear materials accountancy and control at the facility level

    International Nuclear Information System (INIS)

    This paper is the guide to a workshop designed to enable the participants to gain a better understanding of National Safeguards Systems and their functions. The workshop provides the opportunity to address the principal elements of the accounting system to be implemented at the facility level (research reactor and laboratory facilities) as a part of the national safeguards system

  5. Development of the system for academic training of personnel engaged in nuclear material protection, control and accounting in Russia

    International Nuclear Information System (INIS)

    educational problems in area of nuclear materials physical protection, control and accountability (MPC and A) in Russia. General scheme of Russian educational system is considered with main emphasis on the directions under implementation now, namely academic training system, re-training system and specialists qualification upgrade system in MPC and A area. Russian academic training system consists of the educational programs at various levels: Bachelor of Sciences, Master of Sciences, Specialist (also referred to as an Engineer Degree), and professional re-training of the personnel already working in the nuclear field. Currently, only the Master of Sciences Graduate Program is completely developed for the students training. This is taking place at Moscow Engineering Physics Institute (State University, MEPhI), where the fourth generation of Masters has graduated from in May 2003. The graduates are now working at nuclear-related governmental agencies, non-governmental organizations, universities, and nuclear facilities. Development of the system to produce academically trained Russian MPC and A personnel is therefore well underway. MEPhI's MPC and A Engineering Degree Program which currently under development is considered in the paper. Analysis of MPC and A needs at Russian nuclear facilities has demonstrated the Engineering Degree Program is the best way to satisfy these needs and the resulting demands for MPC and A specialists at Russian nuclear enterprises. This paper discusses specific features of the Engineering Degree training required by Russian education legislation and the Russian system of quality control as applied to the training process. The paper summarizes the main joint actions undertaken during the past three years by MEPhI in collaboration with the US Department of Energy and US national laboratories to develop the MPC and A Engineering Degree Program in Russia. These actions include opening a new Engineering Degree specialty, Safeguards and Nonproliferation

  6. Development of the system for academic training of personnel engaged in nuclear material protection, control and accounting in Russia

    International Nuclear Information System (INIS)

    educational problems in area of nuclear materials physical protection, control and accountability (MPC and A) in Russia. General scheme of Russian educational system is considered with main emphasis on the directions under implementation now, namely academic training system, re-training system and specialists qualification upgrade system in MPC and A area. Russian academic training system consists of the educational programs at various levels: Bachelor of Sciences, Master of Sciences, Specialist (also referred to as an Engineer Degree), and professional re-training of the personnel already working in the nuclear field. Currently, only the Master of Sciences Graduate Program is completely developed for the students training. This is taking place at Moscow Engineering Physics Institute (State University, MEPhI), where the fourth generation of Masters has graduated from in May 2003. The graduates are now working at nuclear-related governmental agencies, non-governmental organizations, universities, and nuclear facilities. Development of the system to produce academically trained Russian MPC and A personnel is therefore well underway. MEPhI's MPC and A Engineering Degree Program which currently under development is considered in the paper. Analysis of MPC and A needs at Russian nuclear facilities has demonstrated the Engineering Degree Program is the best way to satisfy these needs and the resulting demands for MPC and A specialists at Russian nuclear enterprises. This paper discusses specific features of the Engineering Degree training required by Russian education legislation and the Russian system of quality control as applied to the training process. The paper summarizes the main joint actions undertaken during the past three years by MEPhI in collaboration with the US Department of Energy and US national laboratories to develop the MPC and A Engineering Degree Program in Russia. These actions include opening a new Engineering Degree specialty, Safeguards and Nonproliferation

  7. Development of a system for academic training of the personnel engaged in nuclear material protection, control and accounting in Russia

    International Nuclear Information System (INIS)

    The main attention in the present paper is focused on discussing the educational problems in the area of nuclear materials physical protection, control and accountability (MPC and A) in Russia. Currently, only the Master of Science Graduate Program has been completely developed for students training. This is taking place at Moscow Engineering Physics Institute (State University, MEPhI), where the sixth generation of Masters has graduated in May 2004. The MPC and A Engineer Degree Program, currently under development at MEPhI, is considered in the paper. This paper discusses specific features of the Engineer Degree training required by the Russian educational legislation and the Russian quality control system as applied to the training process. The paper summarises the main joint actions undertaken during the past three years by MEPhI in collaboration with the US Department of Energy and US National Laboratories for developing the MPC and A Engineer Degree Program in Russia. (author)

  8. Co-operation between Ulba fuel fabrication plant, Kazakhstan and Swedish Nuclear Power Inspectorate to strengthen nuclear material accountancy and control at Ulba

    International Nuclear Information System (INIS)

    The first mission from SKI to Ulba fuel fabrication plant took place in 1992 about a year after the foundation of the Republic of Kazakhstan and at a time when the Kazakhstan nuclear authority was developing its form for operation. During the following years it was a strong political pressure on Kazakhstan to sign the NPT and to put its nuclear installations under IAEA safeguards. Ulba nuclear fuel fabrication plant had a long and successful history of fuel fabrication to the Soviet nuclear program but the nuclear accountancy was based strictly on economic criteria. The existing requirement of the Soviet times was reflected in plant layout and system design. For example the possibility to make an accurate physical inventory taking was not considered. To be able to conform to IAEA requirements a modern system for material accountancy and control had to be established. Ulba personnel, who got support in these activities chiefly by DOE (US) and SKI, Sweden, developed such a system in a remarkably short time. The Swedish activities consisted of, Training course in NMA and C at a fuel fabrication plant in Sweden Seminar on physical inventory taking and support to develop a plan for Ulba for the initial inventory taking. Assistance during the initial physical inventory taking at Ulba. Support to develop a 'Safeguards manual'. The safeguards agreement with IAEA entered into force in 1995 and since then annually physical inventory verifications (PIV) have taken place. An experience from these PIVs is that there is room for improvements in measurement accuracy especially concerning uranium contents in the large number of tanks in the plant. An EU project to provide Ulba with sophisticated equipment for mass/volume measurement in tanks of arbitrary shape is in progress under the leadership of JRC, Ispra. SKI also takes part in this project. SKI have also plans for the future to provide support to Ulba to reduce the material unaccounted for (MUF) at the PIVs

  9. Nuclear material operations manuals

    International Nuclear Information System (INIS)

    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

  10. Nuclear material operations manual

    International Nuclear Information System (INIS)

    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

  11. 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)

    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. Methodologies to determine the Pu content of spent fuel assemblies for input nuclear material accountancy of pyroporcessing

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Taehoon; Shin, Heesung; Kim, Youngsoo; Kim, Hodong [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kwon, Taeje [KEPCO Nuclear Fuel, Daejeon (Korea, Republic of)

    2011-07-01

    This study shows two different non-destructive approaches to determine the Pu mass of spent fuel assemblies, and the analysis results on the errors in their Pu mass. For both methods, the Cm mass of the assembly is obtained based on the neutron measurement results. The Cm ratio of the assembly is determined from the Cm mass and the Pu mass obtained by using either of the two methods. In a comparison of two methods, the second method is simpler than the first and may not need a homogeneously-mixed sample of the spent fuel assembly. On the other hand, the second approach shows larger error in the estimated Pu mass than the first one for many different spent fuel cases of various burnup, initial enrichment, and cooling times. A member state support program for the development of the IAEA safeguards approach for an engineering-scale pyroprocessing facility, which is designated as the Reference Engineering-scale Pyroprocessing Facility(REPF), has been carried out by Korea Atomic Energy Research Institute since 2008. The nuclear material accountancy of the REPF is based on the 'Cm balance' technique. The Pu content of processing materials of pyroprocessing can be determined by measuring the Cm mass of the materials and multiplying it by the Cm ratio. The spent fuel assembly is de-cladded, and the irradiated UO{sub 2} material of the assembly is homogeneously mixed in the homogenization process in order to obtain a representative sample of the spent fuel assembly for determining the mass of Pu, U and Cm elements, as well as the Cm ratio of the campaign. The shipper-receiver difference between the nuclear power plant and HPC of REPF is determined at this point. We found that the error for the Pu mass and Cm ratio determined from the homogenized uranium oxide powder is the most critical for the determination of the material unaccounted for throughout the whole processes. This paper presents two approaches to determine the Pu mass of spent fuel assemblies using non

  13. Materials accounting at Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    The materials accounting system at Los Alamos has evolved from an ''80-column'' card system to a very sophisticated near-real-time computerized nuclear material accountability and safeguards system (MASS). The present hardware was designed and acquired in the late 70's and is scheduled for a major upgrade in fiscal year 1986. The history of the system from 1950 through the DYMAC of the late 70's up to the present will be discussed. The philosophy of the system along with the details of the system will be covered. This system has addressed the integrated problems of management, control, and accounting of nuclear material successfully. 8 refs., 3 figs., 1 tab

  14. Guideline for Evaluating Analytical Chemistry Capabilities and Recommending Upgraded Methods and Instrumentation for Nuclear Material Control and Accountability at Russian Nuclear Facilities

    International Nuclear Information System (INIS)

    Analytical chemistry plays a key role in nuclear material control and accounting (MC and A). A large part of Special Nuclear Material (SNM) inventories and virtually all of the highly attractive SNM inventories are based on sampling bulk materials followed by destructive assay (DA) of these materials. These measurements support MC and A in process control, physical inventory verification, evaluation of the effects of process changes, detecting and resolving shipper-receiver differences, and the resolution of inspector-facility differences. When evaluating these important functions, US Project Teams need to carefully assess the existing Russian analytical chemistry capabilities and to specify appropriate upgrades where needed. This evaluation and the specification of upgrades have proven difficult, in part, because of the highly specialized and technical nature of DA and because of the wide variety of methods and applications. In addition, providing a DA capability to a Russian analytical laboratory requires much more than simply supplying new instrumentation. Experience has shown that DA upgrades at Russian analytical facilities require more support equipment than was originally anticipated by US Teams. The purpose of this guidance document is to: (1) recommend criteria for US Projects Teams to use in their evaluation of Russian DA capabilities; (2) provide a basis for selection of appropriate upgrades where capabilities are inadequate to support MC and A goals; and (3) to provide a list of Da methods suitable for MC and A with the following information: performance and applications information, strengths and limitations, and references and information on cost. Criteria for evaluating existing capabilities and determining appropriate upgrades are difficult to define. However, this is the basic information needed by the US project Teams. Section IV addresses these criteria

  15. Guideline for Evaluating Analytical Chemistry Capabilities and Recommending Upgraded Methods and Instrumentation for Nuclear Material Control and Accountability at Russian Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Russ, G.P.

    1999-10-21

    Analytical chemistry plays a key role in nuclear material control and accounting (MC and A). A large part of Special Nuclear Material (SNM) inventories and virtually all of the highly attractive SNM inventories are based on sampling bulk materials followed by destructive assay (DA) of these materials. These measurements support MC and A in process control, physical inventory verification, evaluation of the effects of process changes, detecting and resolving shipper-receiver differences, and the resolution of inspector-facility differences. When evaluating these important functions, US Project Teams need to carefully assess the existing Russian analytical chemistry capabilities and to specify appropriate upgrades where needed. This evaluation and the specification of upgrades have proven difficult, in part, because of the highly specialized and technical nature of DA and because of the wide variety of methods and applications. In addition, providing a DA capability to a Russian analytical laboratory requires much more than simply supplying new instrumentation. Experience has shown that DA upgrades at Russian analytical facilities require more support equipment than was originally anticipated by US Teams. The purpose of this guidance document is to: (1) recommend criteria for US Projects Teams to use in their evaluation of Russian DA capabilities; (2) provide a basis for selection of appropriate upgrades where capabilities are inadequate to support MC and A goals; and (3) to provide a list of Da methods suitable for MC and A with the following information: performance and applications information, strengths and limitations, and references and information on cost. Criteria for evaluating existing capabilities and determining appropriate upgrades are difficult to define. However, this is the basic information needed by the US project Teams. Section IV addresses these criteria.

  16. Annual Report 2007 - ABACC - Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials; Relatorio anual 2007 - ABACC - Agencia Brasileiro-Argentina de Contabilidade e Controle de Materiais Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This document reports activities during the year 2007 related to: technical activities as application of safeguards; management of the Quadripartite Agreement and the SCCC - Common System for Accounting and Control of Nuclear Materials; training; technical cooperation; outlook for 2008 and; institutional, administrative and financial activities; technical glossary; list of brazilian facilities; list of argentine facilities and a list of institution of nuclear area.

  17. Cooperation between the Russian Federation and the United States to enhance the existing nuclear-material protection, control, and accounting systems at Mayak Production Association

    International Nuclear Information System (INIS)

    The Ministry of the Russian Federation for Atomic Energy (MINATOM) and the US Department of Energy (DOE) are engaged in joint, cooperative efforts to reduce the likelihood of nuclear proliferation by enhancing Material Protection, Control and Accounting (MPC ampersand A) systems in both countries. Mayak Production Association (MPA) is a major Russian nuclear enterprise within the nuclear complex that is operated by MINATOM. This paper describes the nature, scope, and status of the joint, cooperative efforts to enhance existing MPC ampersand A systems at MPA. Current cooperative efforts are focused on enhancements to the existing MPC ampersand A systems at four plants that are operated by MPA and that produce, process, handle and/or store proliferation-sensitive nuclear materials

  18. Cooperation between the Russian Federation and the United States to enhance the existing nuclear-material protection, control, and accounting systems at Mayak Production Association

    International Nuclear Information System (INIS)

    The Ministry of the Russian Federation for Atomic Energy (MINATOM) and the US Department of Energy (DOE) are engaged in joint, cooperative efforts to reduce the likelihood of nuclear proliferation by enhancing Material Protection, Control and Accounting (MPC and A) systems in both countries. Mayak Production Association (Mayak) is a major Russian nuclear enterprise within the nuclear complex that is operated by MINATOM. This paper describes the nature, scope, and status of the joint, cooperative efforts to enhance existing MPC and A systems at Mayak. Current cooperative efforts are focused on enhancements to the existing MPC and A systems at two plants that are operated by Mayak and that produce, process, handle and/or store proliferation-sensitive nuclear materials

  19. Cooperation Between the Russian Federation and the United States to Enhance the Existing Nuclear-Material Protection, Control, and Accounting Systems at Mayak Production Association

    International Nuclear Information System (INIS)

    The Ministry of the Russian Federation for Atomic Energy (MINATOM) and the US Department of Energy (DOE) are engaged in joint, cooperative efforts to reduce the likelihood of nuclear proliferation by enhancing Material Protection, Control and Accounting (MPC and A) systems in both countries. Mayak Production Association (Mayak) is a major Russian nuclear enterprise within the nuclear complex that is operated by lylINATOM. This paper describes the nature, scope, and status of the joint, cooperative efforts to enhance existing MPC and A systems at Mayak. Current cooperative efforts are focused on enhancements to the existing MPC and A systems at two of the plants operated by Mayak that work with proliferation-sensitive nuclear materials

  20. Guidelines for implementation of the Decree of the Czechoslovak Atomic Energy Commission No. 28/1977 on the accountancy and inspection of nuclear materials

    International Nuclear Information System (INIS)

    The Guidelines provide a framework for the accountancy and inspection of nuclear materials and ensure realization of commitments following from the agreement between the Czechoslovak government and the IAEA concerning safeguards in relation to the Non-Proliferation Treaty. It is stipulated that any organization that permanently or temporarily manufactures, uses or keeps nuclear materials covered by the Decree is obliged to keep records and take stock of nuclear materials and to submit periodical reports as defined by the Guidelines. The Guidelines set the beginning and end of record-keeping and define the record-keeping system. Conditions for obtaining a nuclear materials acquisition license are specified, and the responsibilities for implementation of the Guidelines are defined. Details of the nuclear materials record-keeping system and procedures are prescribed, including requirements put on physical stock taking. An overview of reports required from the organizations involved is given. Compliance with the requirements of the Guidelines is supervised by the Czechoslovak Atomic Energy Commission and by IAEA Inspectors. The Guidelines entered into force on 1 April 1982. (J.B.)

  1. Evaluation Execution of Systems of Accounting for and Control of Nuclear Materials in MBA RI-E in Year 2002/2003

    International Nuclear Information System (INIS)

    This activity at the Development Center of Nuclear Fuel and Recycle Technology (P2TBDU) is carried out to obtain and existing problems of nuclear materials accounting. The evaluation is based on the available data and inspection result conducted by BAPETEN and IAEA. In accordance with duty and obligation as the director of nuclear installation, the director of Experimental Fuel Element Installation (EFEI) performed SSAC based on MBA RI-E structure. During this period, routine activities are carried out, with are recording, execution of PIT and report making. Recording is done by filling 2 (two) General Ledgers/Gls for natural uranium and depleted uranium, 14 (four teen) Subsidiary Ledgers/Sls for natural uranium and depleted uranium and also 2 (two) support documents (ICD) for transfer between MBAs and 2 ( two) support documents (IMT) for the transfer between KMPs. Reports made during this period are 2 (two) Inventory Change Report/ICRs, 1 (one) Physical Inventory Listing/PIL and 1 (one) Material Balance Report/MBR. In the execution of SSAC in this period, there are problems between recording which must be done by report maker and that of consumer, that is administrative mistake in document number of Internal Material Transfer (IMT), problems in management of SSAC in which fluent communications system in data transfer from operating data to accounting data have not been established, and problems due to weight difference in each interval of measurements, because of the water content in the material. These problems have resulted in the frequent finding by inspectors during the execution of nuclear material physical of inventory taking which should have been anticipated. For that reason good cooperation is required with the nuclear material consumer in MBA RI-E and supported by knowledge of SSAC improvements in the future. (author)

  2. Nuclear material control in Spain

    International Nuclear Information System (INIS)

    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.)

  3. Nuclear material control in Brazil

    International Nuclear Information System (INIS)

    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.)

  4. ABACC - Brazil-Argentina Agency for Accounting and Control of Nuclear Materials, a model of integration and transparence; ABACC - Agencia Brasileno-Argentina de Contabilidad y Control de Materiales Nucleares, un ejemplo de integracion y transparencia

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Antonio A.; Do Canto, Odilon Marcusso, E-mail: oliveira@abacc.org.br, E-mail: odilon@abacc.org.br [Agencia Brasileno Argentina de Contabilidad y Control de Materiales Nucleares (ABACC), Rio de Janeiro, RJ (Brazil)

    2013-07-01

    Argentina and Brazil began its activities in the nuclear area about the same time, in the 50 century past. The existence of an international nuclear nonproliferation treaty-TNP-seen by Brazil and Argentina as discriminatory and prejudicial to the interests of the countries without nuclear weapons, led to the need for a common system of control of nuclear material between the two countries to somehow provide assurances to the international community of the exclusively peaceful purpose of its nuclear programs. The creation of a common system, assured the establishment of uniform procedures to implement safeguards in Argentina and Brazil, so the same requirements and safeguards procedures took effect in both countries, and the operators of nuclear facilities began to follow the same rules of control of nuclear materials and subjected to the same type of verification and control. On July 18, 1991, the Bilateral Agreement for the Exclusively Peaceful Use of Nuclear Energy created a binational body, the Argentina-Brazil Agency for Accounting and Control of Nuclear Materials-ABACC-to implement the so-called Common System of Accounting and Control of Nuclear materials - SCCC. The deal provided, permanently, a clear commitment to use exclusively for peaceful purposes all material and nuclear facilities under the jurisdiction or control of the two countries. The Quadripartite Agreement, signed in December of that year, between the two countries, ABACC and IAEA completed the legal framework for the implementation of comprehensive safeguards system. The 'model ABACC' now represents a paradigmatic framework in the long process of economic, political, technological and cultural integration of the two countries. Argentina and Brazil were able to establish a guarantee system that is unique in the world today and that consolidated and matured over more than twenty years, has earned the respect of the international community.

  5. US-Russian collaboration for enhancing nuclear materials protection, control, and accounting at the Elektrostal uranium fuel-fabrication plant

    Energy Technology Data Exchange (ETDEWEB)

    Smith, H. [Los Alamos National Lab., NM (United States); Allentuck, J. [Brookhaven National Lab., Upton, NY (United States); Barham, M. [Oak Ridge National Lab., TN (United States); Bishop, M. [Sandia National Labs., Albuquerque, NM (United States); Wentz, D. [Lawrence Livermore National Lab., CA (United States); Steele, B.; Bricker, K. [Pacific Northwest National Lab., Richland, WA (United States); Cherry, R. [USDOE, Washington, DC (United States); Snegosky, T. [Dept. of Defense, Washington, DC (United States). Defense Nuclear Agency

    1996-09-01

    In September 1993, an implementing agreement was signed that authorized collaborative projects to enhance Russian national materials control and accounting, physical protection, and regulatory activities, with US assistance funded by the Nunn-Lugar Act. At the first US-Russian technical working group meeting in Moscow in February 1994, it was decided to identify a model facility where materials protection, control, and accounting (MPC and A) and regulatory projects could be carried out using proven technologies and approaches. The low-enriched uranium (LEU or RBMK and VVER) fuel-fabrication process at Elektrostal was selected, and collaborative work began in June 1994. Based on many factors, including initial successes at Elektrostal, the Russians expanded the cooperation by proposing five additional sites for MPC and A development: the Elektrostal medium-enriched uranium (MEU or BN) fuel-fabrication process and additional facilities at Podolsk, Dmitrovgrad, Obninsk, and Mayak. Since that time, multilaboratory teams have been formed to develop and implement MPC and A upgrades at the additional sites, and much new work is underway. This paper summarizes the current status of MPC and A enhancement projects in the LEU fuel-fabrication process and discusses the status of work that addresses similar enhancements in the MEU (BN) fuel processes at Elektrostal, under the recently expanded US-Russian MPC and A cooperation.

  6. Global nuclear material control model

    International Nuclear Information System (INIS)

    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

  7. Annual Report ABACC 2009 - Brazilian-Argentine Agency for the Accounting and Control of Nuclear Materials; Relatorio anual 2009 - Agencia Brasileiro-Argentina de Contabilidade e Controle de Materiais Nucleares (ABACC)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-07-01

    This document reports the actives during the year 2009 related to: technical activities as application of safeguards; management of the Quadripartite Agreement and the SCCC - Common System for Accounting and Control of Nuclear Materials; training; technical cooperation; institutional, administrative and financial activities; perspectives for 2010; list of inspectors; list of Brazilian and Argentine facilities subject to the Quadripartite Agreement

  8. Insider Threat - Material Control and Accountability Mitigation

    Energy Technology Data Exchange (ETDEWEB)

    Powell, Danny H [ORNL; Elwood Jr, Robert H [ORNL; Roche, Charles T [ORNL

    2011-01-01

    The technical objectives of nuclear safeguards are (1) the timely detection of diversion of significant quantities of nuclear material from peaceful uses to the manufacture of nuclear weapons or other nuclear explosive devices or for purposes unknown and (2) the deterrence of such diversion by the risk of early detection. The safeguards and security program must address both outsider threats and insider threats. Outsider threats are primarily addressed by the physical protection system. Insider threats can be any level of personnel at the site including passive or active insiders that could attempt protracted or abrupt diversion. This could occur by an individual acting alone or by collusion between an individual with material control and accountability (MC&A) responsibilities and another individual who has responsibility or control within both the physical protection and the MC&A systems. The insider threat is one that must be understood and incorporated into the safeguards posture. There have been more than 18 documented cases of theft or loss of plutonium or highly enriched uranium. The insider has access, authority, and knowledge, as well as a set of attributes, that make him/her difficult to detect. An integrated safeguards program is designed as a defense-in-depth system that seeks to prevent the unauthorized removal of nuclear material, to provide early detection of any unauthorized attempt to remove nuclear material, and to rapidly respond to any attempted removal of nuclear material. The program is also designed to support protection against sabotage, espionage, unauthorized access, compromise, and other hostile acts that may cause unacceptable adverse impacts on national security, program continuity, the health and safety of employees, the public, or the environment. Nuclear MC&A play an essential role in the capabilities of an integrated safeguards system to deter and detect theft or diversion of nuclear material. An integrated safeguards system with

  9. Co-operation agreement. The text of the agreement of 25 May 1998 between the International Atomic Energy Agency and the Brazilian-Argentine Agency for accounting and control of nuclear materials

    International Nuclear Information System (INIS)

    The document reproduces the text of the Co-operation Agreement between the International Atomic Energy Agency and the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials which entered into force on 25 May 1998

  10. ABACC: annual report 2012 - Brazilian-Argentine Agency for the Accounting and Control of Nuclear Materials; ABACC: informe annual 2012 - Agencia Brasileiro-Argentina de Contabilidade e Controle de Materiais Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-07-01

    This document reports the actives during the year 2012 related to: technical activities as safeguards application and advances in application of safeguards; main activities conducted in Brazil and main activities developed at ABACC headquarters; management of the Quadripartite Agreement and of the SCCC - Common System for Accounting and Control of Nuclear Materials; training; technical cooperation; institutional, administrative and financial activities; perspectives for 2013; list of inspectors; list of Brazilian and Argentine facilities subject to the Quadripartite Agreement.

  11. Absolute nuclear material assay

    Science.gov (United States)

    Prasad, Manoj K.; Snyderman, Neal J.; Rowland, Mark S.

    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. 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.

  13. New Department of Energy policy and guidance for cost-effectiveness in nuclear materials control and accountability programs

    International Nuclear Information System (INIS)

    Recent Department of Energy (DOE) initiatives have given Departmental nuclear facilities the opportunity to take more credit for certain existing safeguards and security systems in determining operational program protection requirements. New policies and guidance are coupled with these initiatives to enhance systems performance in a cost effective and efficient manner as well as to reduce operational costs. The application of these methods and technologies support safety, the reduction of personnel radiation exposure, emergency planning, and inspections by international teams. This discussion will review guidance and policies that support advanced systems and programs to decrease lifetime operational costs without increasing risk

  14. KrasMAS: Implementation of a nuclear material computerized accounting system at the Mining and Chemical Combine through the Russian/US cooperative MPC and A program

    Energy Technology Data Exchange (ETDEWEB)

    Dorofeev, K.V.; Zhidkov, V.V. [Mining and Chemical Combine, Zheleznogorsk (Russian Federation); Martinez, B.J.; Perry, R.T.; Scott, S.C. [Los Alamos National Lab., NM (United States)

    1998-12-31

    The Russian/US Mining and Chemical Combine (Gorno-Kimichesky Kombinat, GKhK, also referred to as Krasnoyarsk-26) Material Protection, Control and Accounting (MPC and A) project was initiated in June 1996. A critical component of the ongoing cooperative MPC and A enhancements at the GKhK is the implementation of a computerized nuclear material control and accountability (MC and A) system. This system must meet the MC and A requirements of the GKhK by integrating the information generated by numerous existing and new MC and A components in place at the GKhK (e.g., scales, bar-code equipment, NDA measurement systems). During the first phase of this effort, the GKhK adapted CoreMAS (developed at Los Alamos National Laboratory) for use in the PuO{sub 2} storage facility. This included formulation of Web-based user interfaces for plant personnel, Russification of the existing user interface, and at the functional level, modification of the CoreMAS stored procedures. The modified system is referred to as KrasMAS and builds upon completed work on CoreMAS. Ongoing efforts include adding GKhK specific report forms and expanding the functionality of the system for implementation at the radiochemical processing and reactor plants of the GKhK. Collaborations with other Russian facilities for appropriate parts of these efforts will be pursued.

  15. KrasMAS: Implementation of a nuclear material computerized accounting system at the Mining and Chemical Combine through the Russian/US cooperative MPC and A program

    International Nuclear Information System (INIS)

    The Russian/US Mining and Chemical Combine (Gorno-Kimichesky Kombinat, GKhK, also referred to as Krasnoyarsk-26) Material Protection, Control and Accounting (MPC and A) project was initiated in June 1996. A critical component of the ongoing cooperative MPC and A enhancements at the GKhK is the implementation of a computerized nuclear material control and accountability (MC and A) system. This system must meet the MC and A requirements of the GKhK by integrating the information generated by numerous existing and new MC and A components in place at the GKhK (e.g., scales, bar-code equipment, NDA measurement systems). During the first phase of this effort, the GKhK adapted CoreMAS (developed at Los Alamos National Laboratory) for use in the PuO2 storage facility. This included formulation of Web-based user interfaces for plant personnel, Russification of the existing user interface, and at the functional level, modification of the CoreMAS stored procedures. The modified system is referred to as KrasMAS and builds upon completed work on CoreMAS. Ongoing efforts include adding GKhK specific report forms and expanding the functionality of the system for implementation at the radiochemical processing and reactor plants of the GKhK. Collaborations with other Russian facilities for appropriate parts of these efforts will be pursued

  16. Materials control and accountability auditor training

    International Nuclear Information System (INIS)

    As the Department of Energy (DOE) works to standardize the training for individuals performing materials control and accountability (MC and A) functions, the need for a definition of the appropriate training for MC and A auditors has become apparent. In order to meet the DOE requirement for individual training plans for all staff performing MC and A functions, the following set of guidelines was developed for consideration as applicable to MC and A auditors. The application of these guidelines to specific operating environments at individual DOE sites may require modification to some of the tables. The paper presents one method of developing individual training programs for an MC and A auditor or for an MC and A audit group based on the requirements for internal audits and assessments included in DOE Order 5633.3, Control and Accountability for Nuclear Materials

  17. Principal Areas of Activity to Improve the Monitoring of Nuclear Material Security and Accounting in the Russian Federation Ministry of Atomic Energy, within the Framework of the Program of Cooperation with the United States of America

    International Nuclear Information System (INIS)

    One of the major elements of the Russian Federation state system of accounting and control of nuclear materials (SSAC NM) is a 'universal' oversight system for nuclear materials security covering MPC and A at the federal, agency and enterprise levels. Oversight of SSAC NM has always been considered important by the State. In 1951 an Order of the USSR Council of Ministers created a department responsible for the accounting and storing of nuclear materials at the enterprises. The accounting and storing of NM was assigned to the First Central administrative board of the Council of Ministers of the USSR (the former name of the Ministry of Atomic Energy of Russia). Originally this activity included, in general, oversight of the maintenance of secrecy and security during the performance of various kinds of work connected with special production (classified products and materials). Since 1995, beginning with the enactment of the Federal law 'On the use of atomic energy,' this activity has received additional development beyond organizational-methodological activities. Technical equipment and new technologies have been introduced into work on the control of nuclear materials security (for example, means of controlling access to nuclear material, equipment for detecting radiation from nuclear material, etc.). The questions connected to development and perfection of oversight activity are laid out in the 6th section of the Federal targeted program 'Nuclear and radiation safety of Russia' in which the overall working plan for the creation and perfection of the state system accounting and the control of nuclear material in Russia are described. Russian-American collaboration on MPC and A began nearly simultaneously with the enactment of the Law 'On the use of atomic energy.' The purpose of this collaborative program is the introduction of modern technologies in the area of nuclear materials security to the Russian installations using nuclear materials for industrial and

  18. Materials control and accounting (MC and A): the evolutionary pressures

    International Nuclear Information System (INIS)

    Nuclear materials control and accounting systems are subject to pressures of both regulatory and institutional natures. This fact, coupled with the emergence of new technology, is causing evolutionary changes in materials control and accounting systems. These changes are the subject of this paper

  19. Nuclear Material Management Abstract

    International Nuclear Information System (INIS)

    Nevada Test Site (NTS) has transitioned from its historical and critical role of weapons testing to another critical role for the nation. This new role focuses on being a integral element in solving the multiple challenges facing the National Nuclear Security Administration (NNSA) with nuclear material management. NTS is positioned to be a solution for 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 consolidate and modernize the production complex . With respect to the nuclear material stockpile, the NNSA sites are currently reducing the complex nuclear material inventory through disposition and consolidation. 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 assigned activities are accomplished in a safe, secure, efficient, and environmentally responsible manner. NTS activities and challenges will be addressed

  20. Follow-up and accountancy of nuclear materials in EDF's power plants; Le suivi et la comptabilite des matieres nucleaires a electricite de France: retour d'experience d'un exploitant

    Energy Technology Data Exchange (ETDEWEB)

    Cormis, F. de [Electricite de France (EDF), 75 - Paris (France)

    2001-02-01

    This article presents the valuable experience of EDF (French company of electricity) in the field of the follow-up and accountancy of nuclear materials in its facilities. A same software is used in all nuclear power plants. This software allows: -) the follow-up of fuel assemblies from their arrival on the site to their disposal, -) the accountancy of nuclear materials according to international and national regulations, -) the acquisition of physical data concerning fuel assemblies, these data are integrated to a data bank and made available for the different departments of EDF, and -) the collecting and gathering of all the information required by the national or international authorities in charge of controlling nuclear materials. A new software has been designed and is currently tested on several sites. The main improvements concern a more detailed management and a better man-machine interface. (A.C.)

  1. Material Nuclear Culture, Exhibition

    OpenAIRE

    Carpenter, Ele; Mabb, David; Craighead, Alison; Crowe, Nick; Schuppli, Susan; Takeuchi, Kota; Erika, Kobayashi

    2016-01-01

    Material Nuclear Culture is an exhibition of contemporary artists responses to the physical qualities and material traces of the aesthetics, traditions and legacy of nuclear powered submarines in the UK. Whilst the MOD is currently undertaking a public consultation process on how and where to dismantle and store Britain’s old subs the long term problems of storing radioactive waste remain unresolved. The exhibition will include new sculptural, film, sound and installation works by David ...

  2. Smuggling special nuclear materials

    International Nuclear Information System (INIS)

    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)

  3. The State system of accounting for and control of nuclear material (SSAC) of the German Democratic Republic - as of December 1984

    International Nuclear Information System (INIS)

    In the GDR, nuclear material is subject to domestic safeguards implemented by the National Board of Atomic Safety and Radiation Protection, the findings of which are verified by international (IAEA) safeguards in connection with the Treaty on the Nonproliferation of Nuclear Weapons. An overview is given of the main elements and functions of the SSAC, as for example the legal framework; mode, scope, objectives and intrastate organization of nuclear materials controls; system of records; methods of information processing; and reporting to the IAEA. (author)

  4. Feasibility study of passive gamma spectrometry of molten core material from Fukushima Daiichi Nuclear Power Station unit 1, 2, and 3 cores for special nuclear material accountancy - low-volatile FP and special nuclear material inventory analysis and fundamental characteristics of gamma-rays from fuel debris

    International Nuclear Information System (INIS)

    The technologies applied to the analysis of the Three Mile Island accident were examined in a feasibility study of gamma spectrometry of molten core material from the Fukushima Daiichi Nuclear Power Station unit 1, 2, and 3 cores for special nuclear material accountancy. The focus is on low-volatile fission products and heavy metal inventory analysis, and the fundamental characteristics of gamma-rays from fuel debris with respect to passive measurements. The inventory ratios of the low-volatile lanthanides, 154Eu and 144Ce, to special nuclear materials were evaluated by the entire core inventories in units 1, 2, and 3 with an estimated uncertainty of 9%-13% at the 1σ level for homogenized molten fuel material. The uncertainty is expected to be larger locally owing to the use of the irradiation cycle averaging approach. The ratios were also evaluated as a function of burnup for specific fuel debris with an estimated uncertainty of 13%-25% at the 1σ level for units 1 and 2, and most of the fuels in unit 3, although the uncertainty regarding the separated mixed oxide fuel in unit 3 would be significantly higher owing to the burnup dependence approach. Source photon spectra were also examined and cooling-time-dependent data sets were prepared. The fundamental characteristics of high-energy gamma-rays from fuel debris were investigated by a bare-sphere model transport calculation. Mass attenuation coefficients of fuel debris were evaluated to be insensitive to its possible composition in a high-energy region. The leakage photon ratio was evaluated using a variety of parameters, and a significant impact was confirmed for a certain size of fuel debris. Its correlation was summarized with respect to the leakage photopeak ratio of source 154Eu. Finally, a preliminary study using a hypothetical canister model of fuel debris based on the experience at Three Mile Island was presented, and future plans were introduced. (author)

  5. Co-operation Agreement. The Text of the Agreement of 25 May 1998 between the International Atomic Energy Agency and the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials

    International Nuclear Information System (INIS)

    The text of the Co-operation Agreement between the International Atomic Energy Agency and the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials is reproduced herein for the information of all Members. The Agreement entered into force on 25 May 1998, pursuant to Article 8

  6. Nuclear Systems Materials Handbook

    International Nuclear Information System (INIS)

    The NSM Handbook is a multi-volume document being compiled on a continuing basis to meet the broad materials data requirements of those involved in the development of advanced nuclear energy systems. The present focus of the Handbook is upon nuclear systems that have not yet achieved commercial status, with near-term emphasis on the nation's Liquid Metal Fast Breeder Reactor Program. Actual use of the Handbook extends to other advanced nuclear concepts sharing the same needs, and to many nonnuclear engineering activities as well

  7. Control of nuclear materials and materials in Argentina

    International Nuclear Information System (INIS)

    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.)

  8. Energy accounting in nuclear power systems

    International Nuclear Information System (INIS)

    Energy analysis is a systematic way of tracing and accounting for the flows of energy through an industrial system and apportioning a quantity of the primary energy input of the goods and services sent out. The application of energy accounting to nuclear power stations and their growth in generating systems is discussed. Misunderstandings arising from discrepancies and weaknesses in some published simple analyses of hypothetical growth situations are outlined. Results of a more complex energy flow analysis are used to demonstrate that current nuclear energy programs are running at an energy profit. Large fossil fuel savings will occur in a real electrical grid system under anticipated nuclear power growth rates. These savings will give a new dimension in planning the use of fossil energy resources which will still be needed for transport and industrial processes, such as steel-making, for some time to come. (author)

  9. Optimal interface between principal deterrent systems and material accounting

    International Nuclear Information System (INIS)

    The purpose of this study is to find an optimal blend between three safeguards systems for special nuclear material (SNM), the material accounting system and the physical security and material control systems. The latter two are denoted as principal deterrent systems. The optimization methodology employed is a two-stage decision algorithm, first an explicit maximization of expected diverter benefits and subsequently a minimization of expected defender costs for changes in material accounting procedures and incremental improvements in the principal deterrent systems. The probability of diverter success function dependent upon the principal deterrents and material accounting system variables is developed. Within the range of certainty of the model, existing material accounting, material control and physical security practices are justified

  10. Physical protection of nuclear material

    International Nuclear Information System (INIS)

    The Agency's role in relation to physical protection. The Safeguards applied by the Agency pursuant to the agreements to which it is a party have as their objective the detection of diversion of nuclear material to purposes prohibited by the State's undertaking. Also of importance is the question of theft of nuclear material or sabotage of installations by individuals or non-governmental groups, for purposes ranging from personal economic gain to political blackmail. The protection of nuclear material and facilities against illegal acts is an essential supplement to any safeguards system based on accountancy. There is a general recognition of the need for any State to have a system for the physical protection of nuclear material but the obligation to establish such a system does not arise from the safeguards agreement; the Agency cannot oblige a State to do so. It is, however, in a unique position to render advice on the subject, serve as a clearing house of information and co-ordinate the various approaches towards concerted action in this field. From 1971 onward the IAEA has been preparing itself to provide, upon request, technical advice to States setting up systems for the physical protection of nuclear material. In June 1971 it convened a Working Group Meeting on the subject; in November of that year consultants met in Vienna and in March 1972 a Panel meeting was held. These three meetings resulted in the publication, in June 1972, of 'Recommendations for the Physical Protection of Nuclear Material'. From 3-7 February 1975 the IAEA arranged a Consultants Meeting to consider the up-dating and extension of these recommendations. The consultants made a thorough study of the developments since the previous recommendations were drawn up and prepared a working paper for consideration by an Advisory Group meeting planned for 14-18 April 1975. ft is widely recognized that since the previous meetings took place the need for the adequate physical protection of nuclear

  11. Agreement of 13 December 1991 between the Republic of Argentina, the Federative Republic of Brazil, the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials and the International Atomic Energy Agency for the Application of Safeguards

    International Nuclear Information System (INIS)

    The text of the Agreement (and the Protocol thereto) between the Republic of Argentina, the Federative Republic of Brazil, the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials and the International Atomic Energy Agency for the Application of Safeguards is reproduced in this document for the information of all Members. The Agreement was approved by the Agency's Board of Governors on 7 December 1991 and signed in Vienna on 13 December 1991

  12. Transportation of nuclear materials

    International Nuclear Information System (INIS)

    The United States Department of Energy's Transportation Management Division (TMD) is responsible for assuring that the Department's shipments of nuclear materials are made in a safe, secure, efficient and economic manner. While stringent regulatory standards for materials packaging, carrier training and shipment routing are designed and followed to ensure a high level of f = safety in transportation, concerns about the risks of such shipments are often significant within communities along a shipping route. To address these concerns, DOE/TMD is 1988 began a cooperative program with public safety, health and planning professionals from the large city and urban county membership of the Urban Consortium for Technology Initiatives. With a focus on local issues, these practitioners defined a series of general concerns and assistance needs in areas of coordination, training, information and responder resources, marking and placarding, and costs and education

  13. Regulation on nuclear materials In Indonesia

    International Nuclear Information System (INIS)

    Indonesia belongs to those countries which actively utilizes atomic energy for peaceful purposes. In order to prevent the deviation of the purpose of nuclear energy utilization and nuclear security, there is a need to enact governmental regulation according to the Act No. 10 Year 1997 on Nuclear Energy article 4.a. The utilization of nuclear energy shall be controlled properly in order to comply with the safety regulations. Safety regulation consists of regulation, licensing and inspection established by regulatory body according to the Act No. 10 Year 1997 article 4.b. The Presidential Decree No. 76/1998 on the regulation of the utilization of nuclear energy in Indonesia is vested to Bapeten (Badan Pengawas Tenaga Nuklir - Nuclear Energy Regulatory Agency). Any body who proposes a license to use nuclear materials shall fulfil and comply with the regulation established by Government and Regulatory Body. According to Chapter 3 article 10 paragraph 1 of Government Regulation (GR) No. 29, Year 2008, any person or institution that will utilize nuclear energy shall posses license issued by Regulatory Body. GR No. 43 Year 2006 Chapter 3 article 15 states that the utility proposing license for reactor commissioning shall have the license of nuclear material utilization. Approval on certification of nuclear material, transportation licensing and export of spent fuel are regulated in GR No 26 Year 2002 on the safety of Radioactive Material Transportation. GR No. 29 Year 2008 Chapter III article 16 governs that the licensee shall posses System of Accounting for and Control of Nuclear Material and system of Physical Protection of Nuclear Material. GR No 43 year 2006 Chapter 3 article 12 and Bapeten Chainnan Regulation (BCR) No. 3 year 2006 Chapter 2 article 11 state that utilities proposing a construction license shall submit DIQ (Design Information Questionnaire for SSAC) and preliminary physical protection program. As the authorized institution, Bapeten has established the

  14. Electrochemically-Modulated Separations for Material Accountability Measurements

    Energy Technology Data Exchange (ETDEWEB)

    Arrigo, Leah M.; Liezers, Martin; Douglas, Matthew; Green, Michael A.; Farmer, Orville T.; Schwantes, Jon M.; Peper, Shane M.; Duckworth, Douglas C.

    2010-05-07

    The Safeguards community recognizes that an accurate and timely measurement of accountable material mass at the head-end of the facility is critical to a modern materials control and accountability program at fuel reprocessing plants. For material accountancy, it is critical to detect both acute and chronic diversions of nuclear materials. Therefore, both on-line nondestructive (NDA) and destructive analysis (DA) approaches are desirable. Current methods for DA involve grab sampling and laboratory based column extractions that are costly, hazardous, and time consuming. Direct on-line gamma measurements of Pu, while desirable, are not possible due to contributions from other actinide and fission products. A technology for simple, online separation of targeted materials would benefit both DA and NDA measurements.

  15. Computerized real-time materials accountability system for safeguards material control

    International Nuclear Information System (INIS)

    A real-time, computer-based system is described which provides safeguards material control at the Oak Ridge National Laboratory. Originally installed in 1972 to provide computerized real-time fissile materials accountability for criticality control purposes, the system has been expanded to provide accountability of all source and nuclear materials (SNM) and to utilize the on-line inventory files in support of the Laboratory physical protection and surveillance procedures. (auth)

  16. Improved attribute sampling plans for materials accounting

    International Nuclear Information System (INIS)

    The Safeguards Systems Group at the Los Alamos National Laboratory has been requested to study attribute sampling plans requiring minimal sample sizes for the purpose of reducing personnel time and radiation exposure in item inventories of nuclear materials. Results indicate that double sampling plans can generally reduce the work effort by at least 30% compared with the single sampling plans currently used at the Los Alamos plutonium facility. Such innovations should be applicable to any DOE facility engaged in processing nuclear materials, particularly in low-turnover storage areas. Future work includes the study of multiple sampling plans as a possible procedure for further reduction of sample sizes

  17. Human performance: An essential element in materials control and accountability

    International Nuclear Information System (INIS)

    The importance of the role of human performance in the successful and effective operation of many activities throughout many industries has been well documented. Most closely related to the materials control and accountability area is the work in human factors that has been ongoing in the U.S. nuclear industry since the Three Mile Island Nuclear Power Plant accident in 1979. Research related to the role of human reliability, human-system interface, and organization and management influences has been and is still being conducted to identify ways to enhance the safe and effective operation of nuclear facilities. This paper will discuss these human performance areas and how they relate to the materials control and accountability area. Particular attention will be focussed on the notion of open-quotes safety cultureclose quotes and how it can be defined and measured for understanding the values and attitudes held by individuals working in the materials control area. It is widely believed that the culture of an organization, which reflects the expectations and values of the management of an organization, is a key element to the operation of that organization. The human performance element is one which has not received a great deal of consideration in the materials control and accountability area and yet it will be demonstrated that it is an essential component to ensure the success of safeguards activities

  18. Nuclear material control in the United States

    International Nuclear Information System (INIS)

    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

  19. Global nuclear material flow/control model

    International Nuclear Information System (INIS)

    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

  20. The nuclear safety account and the Chernobyl nuclear power plant

    International Nuclear Information System (INIS)

    In 1993, the G-7 officially proposed that the European Bank for Reconstruction and Development set up the Nuclear Safety Account (NSA) and act as the Account's secretariat. The Bank's Board of Directors approved this proposal and the Rules of the NSA on 22 March 1993 and the NSA became effective on 14 April 1993. The NSA finances, through grants, operational and near-term technical safety improvements for Soviet-designed nuclear reactors in the countries of the former Soviet Union, central and eastern Europe. Priority is given to those reactors which present the highest level of risk that can be significantly reduced by short-term and cost-effective safety improvements, and which are necessary to ensure the continuing electricity supply in the region. Efforts are therefore focused on WWER 440/230 and RBMK types of reactors and on the purchase of equipment as opposed to studies, which a number of donors already fund. Finance from the NSA is not used to extend the operating lifetime of unsafe reactors

  1. 78 FR 67223 - Proposed Guidance for Fuel Cycle Facility; Material Control and Accounting Plans and Completing...

    Science.gov (United States)

    2013-11-08

    ... for Fuel Cycle Facility; Material Control and Accounting Plans and Completing NRC Form 327 and Amendments to Material Control and Accounting Regulations; Proposed Rules #0;#0;Federal Register / Vol. 78... and Accounting Plans and Completing NRC Form 327 AGENCY: Nuclear Regulatory Commission. ACTION:...

  2. Nuclear measurements and reference materials

    International Nuclear Information System (INIS)

    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 235U 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 7Li and were started for the tritium production cross-section of 9Be. Reference materials of uranium minerals and ores were prepared. Special nuclear targets were prepared. A batch of 250 g of Pu02 was characterized in view of certification as reference material for the elemental assay of plutonium

  3. The physical protection of nuclear material and nuclear facilities

    International Nuclear Information System (INIS)

    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

  4. Coprecal: materials accounting in the modified process

    International Nuclear Information System (INIS)

    This report presents the design and evaluation of an advanced materials accounting system for a uranium-plutonium nitrate-to-oxide coconversion facility based on the General Electric Coprecal process as modified by Savannah River Laboratory and Plant and DuPont Engineering. The modifications include adding small aliquot tanks to feed the process and reconfiguring the calciner filter systems. Diversion detection sensitivities for the modified Coprecal process are somewhat better than the original Coprecal design, but they are still significantly worse than a same-sized conversion facility based on the oxalate (III) precipitation process

  5. Nuclear raw materials

    International Nuclear Information System (INIS)

    It is clear that in the next decades there will be a substantial and increasing demand for uranium to fuel nuclear power stations. In a developing country, the discovery and development of uranium resources can be of importance either for the development of national nuclear power or for the commercial export of uranium. As the time taken between the start of a uranium exploration program and the uranium production stage.may be of the order of 6 - 10 years, it is now opportune to start new exploration so that advantage of the increased demand in the mid-1970s may be achieved. Thorium will also be of interest, but in the more distant future when the thorium cycle for advanced converters and breeder reactors is fully developed

  6. Nuclear power plant cable materials :

    Energy Technology Data Exchange (ETDEWEB)

    Celina, Mathias Christopher; Gillen, Kenneth T; Lindgren, Eric Richard

    2013-05-01

    A selective literature review was conducted to assess whether currently available accelerated aging and original qualification data could be used to establish operational margins for the continued use of cable insulation and jacketing materials in nuclear power plant environments. The materials are subject to chemical and physical degradation under extended radiationthermal- oxidative conditions. Of particular interest were the circumstances under which existing aging data could be used to predict whether aged materials should pass loss of coolant accident (LOCA) performance requirements. Original LOCA qualification testing usually involved accelerated aging simulations of the 40-year expected ambient aging conditions followed by a LOCA simulation. The accelerated aging simulations were conducted under rapid accelerated aging conditions that did not account for many of the known limitations in accelerated polymer aging and therefore did not correctly simulate actual aging conditions. These highly accelerated aging conditions resulted in insulation materials with mostly inert aging processes as well as jacket materials where oxidative damage dropped quickly away from the air-exposed outside jacket surface. Therefore, for most LOCA performance predictions, testing appears to have relied upon heterogeneous aging behavior with oxidation often limited to the exterior of the cable cross-section a situation which is not comparable with the nearly homogenous oxidative aging that will occur over decades under low dose rate and low temperature plant conditions. The historical aging conditions are therefore insufficient to determine with reasonable confidence the remaining operational margins for these materials. This does not necessarily imply that the existing 40-year-old materials would fail if LOCA conditions occurred, but rather that unambiguous statements about the current aging state and anticipated LOCA performance cannot be provided based on

  7. Safeguards and Nuclear Material Management

    International Nuclear Information System (INIS)

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

  8. Accounting Systems for Heavy Water and Fissionable Materials

    International Nuclear Information System (INIS)

    Detailed accounting and reporting procedures used by Atomic Energy of Canada Limited (AECL) for maintaining adequate records and control of heavy water supplies and stocks of fissionable materials are described, along with the duties and responsibilities of those administering the system. An appraisal is made of these procedures with respect to their adaptability for use in rapidly expanding research and power programmes. In particular the use of electronic data processing equipment is evaluated. A senior management committee is responsible for ensuring that there is a proper system for recording, reporting and controlling fissionable materials. The Production Planning and Control Branch (Pp and C B) of the Operations Division at the Chalk River Nuclear Laboratories (CRNL) is responsible to the committee for keeping the over-all records and for the general administration of the system. The duties involved are detailed in the report. The system for fissionable materials is segregated into several accountability units 15 of which are allocated to AECL departments and the others to Canadian industries and research organizations. A control ledger is kept by PP and CB for each of the units; however, the units are responsible for preparing detailed accounts of all material under their jurisdiction. The basic recording procedures covering the movement Of materials between units, the changing of forms within units, the handling of gains and losses, and disposals, are outlined in the report. The transfer of this data to IBM cards, the ultimate processing through an IBM 1401 computer and the preparation of reports for management approval are described. The heavy-water accounting system based on the same principles as used for the fissionable materials is explained. In this case the control ledger lists the pounds of D2O allocated to each of the 15 accountability units. Again the basic recording methods and the use of a computer system are outlined. (author)

  9. Nuclear Systems Materials Handbook. [Materials requirements for nuclear energy systems

    Energy Technology Data Exchange (ETDEWEB)

    Marchbanks, M.F; Moen, R.A.; Irvin, J.E.

    1976-01-01

    The NSM Handbook is a multi-volume document being compiled on a continuing basis to meet the broad materials data requirements of those involved in the development of advanced nuclear energy systems. The present focus of the Handbook is upon nuclear systems that have not yet achieved commercial status, with near-term emphasis on the nation's Liquid Metal Fast Breeder Reactor Program. Actual use of the Handbook extends to other advanced nuclear concepts sharing the same needs, and to many nonnuclear engineering activities as well.

  10. Nuclear technology and materials science

    International Nuclear Information System (INIS)

    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)

  11. Materials challenges for nuclear systems

    Directory of Open Access Journals (Sweden)

    Todd Allen

    2010-12-01

    Full Text Available The safe and economical operation of any nuclear power system relies to a great extent, on the success of the fuel and the materials of construction. During the lifetime of a nuclear power system which currently can be as long as 60 years, the materials are subject to high temperature, a corrosive environment, and damage from high-energy particles released during fission. The fuel which provides the power for the reactor has a much shorter life but is subject to the same types of harsh environments. This article reviews the environments in which fuels and materials from current and proposed nuclear systems operate and then describes how the creation of the Advanced Test Reactor National Scientific User Facility is allowing researchers from across the United States to test their ideas for improved fuels and materials.

  12. Volume measurement system for plutonium nitrate solution and its uncertainty to be used for nuclear materials accountancy proved by demonstration over fifteen years

    International Nuclear Information System (INIS)

    An accurate volume measurement system for plutonium nitrate solution stored in an accountability tank with dip-tubes has been developed and demonstrated over fifteen years at the Plutonium Conversion Development Facility of the Japan Atomic Energy Agency. As a result of calibrations during the demonstration, it was proved that measurement uncertainty practically achieved and maintained was less than 0.1% (systematic character) and 0.15% (random) as one sigma which was half of the current target uncertainty admitted internationally. It was also proved that discrepancy between measured density and analytically determined density was less than 0.002 g·cm-3 as one sigma. These uncertainties include effects by long term use of the accountability tank where cumulative plutonium throughput is six tons. The system consists of high precision differential pressure transducers and a dead-weight tester, sequentially controlled valves for periodical zero adjustment, dampers to reduce pressure oscillation and a procedure to correct measurement biases. The sequence was also useful to carry out maintenances safely without contamination. Longevity of the transducer was longer than 15 years. Principles and essentials to determine solution volume and weight of plutonium, measurement biases and corrections, accurate pressure measurement system, maintenances and diagnostics, operational experiences, evaluation of measurement uncertainty are described. (author)

  13. Materials science for nuclear detection

    Directory of Open Access Journals (Sweden)

    Anthony Peurrung

    2008-03-01

    Full Text Available The increasing importance of nuclear detection technology has led to a variety of research efforts that seek to accelerate the discovery and development of useful new radiation detection materials. These efforts aim to improve our understanding of how these materials perform, develop formalized discovery tools, and enable rapid and effective performance characterization. We provide an overview of these efforts along with an introduction to the history, physics, and taxonomy of radiation detection materials.

  14. Strength of structural materials of nuclear reactors

    International Nuclear Information System (INIS)

    The monography reviews the phenomenon of stress-corrosion craving of zirconium-alloy fuel cans in the nuclear fuel fission products and ways of its prevention. Equations of creep and limiting state of FBR core materials were derived on the basis of the concept of deformation processes unity taking into account the degree of structural stability of alloys, temperature, nonstationary loading and aggressive media effects. Equations of durability under joint quasistatic and cyclic loading are developed. 146 refs.; 91 figs.; 16 tabs

  15. Computerized nuclear material system at Sandia National Laboratories

    International Nuclear Information System (INIS)

    SNLA developed and implemented a nuclear material control and accountability system on an HP 3000 minicomputer. The Sandia Nuclear Materials Computer System (SNMCS) which became operative in January 1980 provides: control of shipments and receivals of nuclear material, control of internal transfers of nuclear material, automated inventory with a bar code system, control of inventory adjustments, automated reporting/transmitting to other contractors and operations offices, automated ledgers and journals for material weights and costs, and interface to the Albuquerque Operations Office (ALO) Automated 741 System

  16. Safety protection of nuclear facilities and nuclear materials

    International Nuclear Information System (INIS)

    Safety protection is discussed of nuclear facilities and of nuclear materials, which is a specific element of guaranteeing nuclear safety. Its task is to maximally restrict the risk of misuse of nuclear facilities and nuclear materials for endangering human lives and health and the environment. Concrete requirements for the barriers and technical means and for security of nuclear facilities and nuclear materials are based on this approach. In the CSSR, a legal norm is being prepared that will enact the said requirements for safety protection of nuclear facilities and nuclear materials. (Z.M.)

  17. Nuclear Forensic Materials and Methods

    Science.gov (United States)

    Hutcheon, I. D.; Grant, P. M.; Moody, K. J.

    A short history and treatment of the various aspects of nuclear forensic analysis is followed by a discussion of the most common chemical procedures, including applications of tracers, radioisotopic generators, and sample chronometry. Analytic methodology discussed includes sample preparation, radiation detection, various forms of microscopy, and mass-spectrometric techniques. The chapter concludes with methods for the production and treatment of special nuclear materials and with a description of several actual case studies conducted at Livermore.

  18. Strategic special nuclear material Inventory Differences

    Science.gov (United States)

    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. If necessary, an operation may be shut down until an ID is resolved.

  19. Nuclear data information system for nuclear materials

    International Nuclear Information System (INIS)

    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/Li2O/H2O(SUS), 9Cr-2W/Li2O/H2O(RAF), V alloy/Li/Be(V), and SiC/Li2ZrO3/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)

  20. 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

  1. Study on Seal Technology for Nuclear Material Control

    Institute of Scientific and Technical Information of China (English)

    2002-01-01

    The seals have important application in nuclear safeguards, and are designed to record unauthorizedaccess or entry to inspected material and equipment. They can provide assurance for the continuity andintegrity of nuclear material accountancy. It is very useful to improve the inspection efficiency by means

  2. LECI Department of Nuclear Materials

    International Nuclear Information System (INIS)

    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

  3. MSFC Nuclear Propulsion Materials Development

    Science.gov (United States)

    Rogers, J. R.; Cook, B.

    2004-01-01

    Nuclear propulsion systems for spacecraft applications present numerous technical challenges for propulsion systems. They have been the focus of a recent NRA. Challenges inclue: a nuclear reactor subsystem to produce thermal energy; a power conversion subsystem to convert the thermal energy into electrical energy; a propulsion subsystem that utilizes Hall effect thrusters; thruster technologies and high temperature materials to support subsystems. The MSFC Electrostatic Levitation (ESL) Facility provides an ideal platform for the study of high temperature and reactive materials. An overview of the facility and its capabilities will be presented.

  4. Material Protection, Accounting, and Control Technologies (MPACT) Advanced Integration Roadmap

    Energy Technology Data Exchange (ETDEWEB)

    Durkee, Joe W. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Cipiti, Ben [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Demuth, Scott Francis [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Fallgren, Andrew James [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Jarman, Ken [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Li, Shelly [Argonne National Lab. (ANL), Argonne, IL (United States); Meier, Dave [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Miller, Mike [Argonne National Lab. (ANL), Argonne, IL (United States); Osburn, Laura Ann [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Pereira, Candido [Argonne National Lab. (ANL), Argonne, IL (United States); Dasari, Venkateswara Rao [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Ticknor, Lawrence O. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Yoo, Tae-Sic [Argonne National Lab. (ANL), Argonne, IL (United States)

    2016-09-30

    The development of sustainable advanced nuclear fuel cycles is a long-term goal of the Office of Nuclear Energy’s (DOE-NE) Fuel Cycle Technologies program. The Material Protection, Accounting, and Control Technologies (MPACT) campaign is supporting research and development (R&D) of advanced instrumentation, analysis tools, and integration methodologies to meet this goal (Miller, 2015). This advanced R&D is intended to facilitate safeguards and security by design of fuel cycle facilities. The lab-scale demonstration of a virtual facility, distributed test bed, that connects the individual tools being developed at National Laboratories and university research establishments, is a key program milestone for 2020. These tools will consist of instrumentation and devices as well as computer software for modeling, simulation and integration.

  5. Accounting for maintenance in the design of nuclear power plants

    International Nuclear Information System (INIS)

    The objective of the CIDEM project (French acronym for Design Integrating Availability, Operating Experience and Maintenance) is to control the per-kW production cost of future Electricite de France REP 2000 nuclear plants. In particular, such cost control requires accounting for maintenance and logistic support from the time of design of the future installations. This technical and economic optimization is based on assessment and comparison of possible choices in terms of materials and maintenance, and on the search for potential improvements. In the Basic Design phase, the method involves identifying reference components which are supposed highly similar to the components to be designed. In the Construction phase, it culminates in the early definition of a detailed maintenance and support plant. To be effective, the approach requires realistic tailoring of the studies to be undertaken, and the participation of multidisciplinary teams working in the framework of concurrent engineering. (author)

  6. Nuclear Material (Offences) Act 1983

    International Nuclear Information System (INIS)

    The main purpose of this Act is to enable the United Kingdom to ratify the Convention on the Physical Protection of Nuclear Material which opened for signature at Vienne and New York on 3 March 1980. The Act extends throughout the United Kingdom. (NEA)

  7. Annual report and accounts 1994/95: Scottish Nuclear

    International Nuclear Information System (INIS)

    The Annual Report and Accounts for Scottish Nuclear are presented for the year 1994/1995. Scottish Nuclear Limited produces about half of Scotland's electricity requirement in its advanced gas-cooled reactors (AGRs) at Hunterston and Torness. It also has responsibility for decommissioning the Hunterston A Magnox nuclear power station. The role of the company in the international arena and as part of the United Kingdom's electric power industry, following privatisation, are discussed. (UK)

  8. Protecting Material Control and Accounting Systems from falsification by insiders

    Energy Technology Data Exchange (ETDEWEB)

    Sacks, I.J.

    1986-01-01

    Over the past several years, DOE facilities handling special nuclear material have been upgrading their material control and accounting (MCandA) systems to protect against insiders. Most of the systems analyzed were found to be relatively secure, but they did contain some insider vulnerabilities. The process of creating the information flow models used to analyze these systems has provided insight into general design features which can eliminate these vulnerabilities. Two of the major features characterizing secure MCandA systems are data independence and data verification. In this paper, these features are illustrated by means of typical, vulnerable MCandA procedures and by the steps needed to correct those vulnerabilities. Based on their assessment experience, the authors provide design guidance which could eliminate many insider vulnerabilities.

  9. The nuclear safeguards system and the process of global governance accountability

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-07-01

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

  10. The nuclear safeguards system and the process of global governance accountability

    International Nuclear Information System (INIS)

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

  11. Experience of air transport of nuclear fuel material in Japan

    International Nuclear Information System (INIS)

    Certified Reference Materials (hereafter called as to CRMs), which are indispensable for Quality Assurance and Material Accountability in nuclear fuel plants, are being provided by overseas suppliers to Japanese nuclear entities as Type A package (non-fissile) through air transport. However, after the criticality accident at JCO in Japan, special law defining nuclear disaster countermeasures (hereafter called as to the LAW) has been newly enforced in June 2000. Thereafter, nuclear fuel materials must meet not only to the existing transport regulations but also to the LAW for its transport

  12. Analytical chemistry of nuclear materials

    International Nuclear Information System (INIS)

    The second panel on the Analytical Chemistry of Nuclear Materials was organized for two purposes: first, to advise the Seibersdorf Laboratory of the Agency on its future programme, and second, to review the results of the Second International Comparison of routine analysis of trace impurities in uranium and also the action taken as a result of the recommendations of the first panel in 1962. Refs, figs and tabs

  13. Measurement and accounting of the minor actinides produced in nuclear power reactors

    Energy Technology Data Exchange (ETDEWEB)

    Stewart, J.E.; Walton, R.B.; Phillips, J.R.; Hsue, S.T.; Eccleston, G.W.; Menlove, H.O.; Davidson, J.M.; Stanbro, W.D.

    1996-01-01

    Because of their value as nuclear fuels and their impact on long-term storage of high-level radioactive waste, measurement and accounting for minor actinides (MAs) produced in nuclear power reactors are becoming significant issues. This report attempts to put the issues in perspective by reviewing the commercial nuclear fuel cycle with emphasis on reprocessing plants and key measurement points therein. Radiation signatures and characteristics are compared and contrasted for special nuclear materials (SNMs) and MAs. Also, inventories and relative amounts of SNMs and MAs are generally described for irradiated nuclear fuel and reprocessing plants. The bulk of the report describes appropriate measurement technologies, capabilities, and development needs to satisfy material accounting requirements for MAs, with emphasis on adaptation of current technologies. Recommendations for future systems studies and development of measurement methods are also included. 38 refs., 3 figs., 12 tabs.

  14. Measurement and accounting of the minor actinides produced in nuclear power reactors

    International Nuclear Information System (INIS)

    Because of their value as nuclear fuels and their impact on long-term storage of high-level radioactive waste, measurement and accounting for minor actinides (MAs) produced in nuclear power reactors are becoming significant issues. This report attempts to put the issues in perspective by reviewing the commercial nuclear fuel cycle with emphasis on reprocessing plants and key measurement points therein. Radiation signatures and characteristics are compared and contrasted for special nuclear materials (SNMs) and MAs. Also, inventories and relative amounts of SNMs and MAs are generally described for irradiated nuclear fuel and reprocessing plants. The bulk of the report describes appropriate measurement technologies, capabilities, and development needs to satisfy material accounting requirements for MAs, with emphasis on adaptation of current technologies. Recommendations for future systems studies and development of measurement methods are also included. 38 refs., 3 figs., 12 tabs

  15. 76 FR 28193 - Amendments to Material Control and Accounting Regulations

    Science.gov (United States)

    2011-05-16

    ... COMMISSION 10 CFR Parts 72, 74, and 150 RIN 3150-AI61 Amendments to Material Control and Accounting... proposed rule language concerning the NRC's proposed amendments to the material control and accounting (MC... FNMC is an outdated term, as it does not include ``accounting,'' and thus does not fully describe...

  16. 78 FR 67225 - Amendments to Material Control and Accounting Regulations

    Science.gov (United States)

    2013-11-08

    ... COMMISSION 10 CFR Parts 40, 70, 72, 74, and 150 RIN 3150-AI61 Amendments to Material Control and Accounting... Commission (NRC) is proposing to amend its regulations for material control and accounting (MC&A) of special... for control and accounting of SNM that is held by a licensee. The MC&A regulations ensure that...

  17. The changing role of Material Control and Accountability at Savannah River Site

    International Nuclear Information System (INIS)

    As Westinghouse Savannah River Company has been faced with the challenge of better meeting DOE needs with reduced budgets and manpower, the Materials Control and Accountability (MC ampersand A) organization has taken a hard look at its roles and responsibilities. A MC ampersand A program is composed of many functions that can not only meet safeguards needs, but can be used by several organizations across the site to meet their needs as well. These functions include nuclear material measurements, tracking, accounting, and inventory control. The infrastructure in place to provide these functions for accountable nuclear materials requires only a few adjustments to expand to other areas of nuclear materials accounting and control. By integrating several organizations' requirements, the MC ampersand A section can allow line organizations to reduce their costs and rely on the section to better service their needs. On the reverse side, MC ampersand A has completed several cost reduction measures that will allow it to expand its role with no increased costs. The roles and responsibilities of the nuclear material control and accountability program should be expanded. The program's existing information infrastructure, and knowledge and experience in nuclear material measurements and safeguards can be built upon to meet the needs of new areas such as waste management and decommissioning and decontamination while continuing to support the existing processing. and storage efforts of current facilities

  18. Analytical chemistry of nuclear materials

    International Nuclear Information System (INIS)

    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

  19. Materials control and accountability challenges associated with plutonium inventories

    International Nuclear Information System (INIS)

    There are currently many initiatives underway within the Department of Energy (DOE) to safely and securely manage large plutonium inventories arising from weapons dismantlement, changing missions and facility operations. Plutonium inventory information is increasingly accessible to the public as a result of the secretary of energy's openness initiative. As a result, knowledge of these inventories and levels to which the department has accounted for and controlled these inventories, will be under increased scrutiny from a variety of interest groups. The quality of this accountability data and what this data means will greatly influence the public's perception of how the US is protecting its plutonium inventories. In addition, the department's safeguards program provides an essential basis for the application of International Atomic Energy Agency (IAEA) safeguards that, in addition to possibly other international control regimes, will be in place over a large portion of these future inventories. The capability and functionality of the department's nuclear safeguards program will be important contributors to the success of US programs for the responsible stewardship of these vast plutonium inventories. This paper discusses some of the challenges, in terms of specific issues relating to one part of the department's safeguards program--materials control and accountability (MC and A)--to meet the growing domestic and international requirements and expectations associated with these plutonium inventories

  20. On accounting difficulties: risks related to nuclear power

    International Nuclear Information System (INIS)

    An extreme risk has a very slight probability but potentially heavy consequences. Despite the existence of 3 accountancy methods for dealing with them (provisions, contingent liabilities and insurance), the transposition of such risks into financial statements is based on a sequential analysis of both the probability of the risk happening and the ability to estimate the effects. This method keeps us from taking into account risks with a highly uncertain probability of occurrence, such as accidents at nuclear power plants - independently of the 'amount' at stake. As management reports from firms concerned by nuclear risks show, the diffusion of qualitative information does not offset this gap in bookkeeping. (authors)

  1. 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.

  2. 48 CFR 9904.411 - Cost accounting standard-accounting for acquisition costs of material.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 7 2010-10-01 2010-10-01 false Cost accounting standard-accounting for acquisition costs of material. 9904.411 Section 9904.411 Federal Acquisition Regulations System COST ACCOUNTING STANDARDS BOARD, OFFICE OF FEDERAL PROCUREMENT POLICY, OFFICE OF MANAGEMENT...

  3. PROBLEMS TAX ACCOUNTING OF MATERIALS IN INNOVATIVE BUSINESS ENVIRONMENT

    OpenAIRE

    Shulepina S. A.

    2014-01-01

    The article presents the key information about the nuances of forming material costs in order to calculate the income tax. Learn how to recognize the costs as material. There are changes in tax accounting above costs in 2015

  4. Identification of unknown nuclear material

    Energy Technology Data Exchange (ETDEWEB)

    Nicolaou, G. [University of Thrace, Department of Electrical and Computer Engineering, Laboratory of Nuclear Technology, Kimmerria Campus, 67100 Xanthi (Greece)

    2010-07-01

    Aim: provenance determination of unknown nuclear material: - demonstrated for spent nuclear fuel; - information sought for unknown: fuel type, reactor type where fuel was irradiated, final burnup; Using an isotopic finger-printing method: - U, Pu or Pu isotopics or fission products; - simulations of fuel evolution during irradiation, using ORIGEN; - multivariate statistical tools. Fuel considered: simulated commercial spent fuel for a range of burnups: - PWR UO{sub 2} 3.1% and 3.5% {sup 235}U, - PWR thermal MOX, - BWR UO{sub 2} 3.2% {sup 235}U, - CANDU-N natural U, - CANDU-S UO{sub 2} 3.2% {sup 235}U, - fast Reactor MOX; simulated commercial spent fuel for a range of burnups: - PWR UO{sub 2} 3.1% and 3.5% {sup 235}U, - PWR thermal MOX, - BWR UO{sub 2} 3.2% {sup 235}U, - CANDU-N natural U, - CANDU-S UO{sub 2} 3.2% {sup 235}U, - fast Reactor MOX; 'unknown' spent fuel: - PWR 1: UO{sub 2} 3.1% {sup 235}U (26 GWd/t), - PWR 2: UO{sub 2} 3.1% {sup 235}U (32 GWd/t). Procedures: U, Pu or Pu isotopic compositions or fission products: - isotopic composition of unknown spent fuel, - simulated for commercial spent fuel from a range of nuclear power reactors {yields} comparison of compositions through factor analysis {yields} unknown has the provenance of the commercial spent fuel with which it exhibits the most similar composition. In conclusion: different reactor-fuel types well resolved; fuel and reactor type accurately predicted; burnup predicted to within 5% of declared; different reactor-fuel types. (authors)

  5. The environmental accounting in the nuclear fuel cycle; A contabilidade ambiental no ciclo do combustivel nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Komatsu, Cintia Nagako [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), SP (Brazil)]. E-mail: cintia@ctmsp.mar.mil.br; Aquino, Afonso Rodrigues de [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)]. E-mail: araquino@ipen.br

    2006-11-15

    This paper illustrates how accountancy can contribute to conservation, protection and the recovery of the environment. Firstly, the appearance of accountancy, its performance fields, its terminologies and even the Environmental Accounting Definition is approached, bringing the social balance as a tool for making decisions in the social field. Environmental Accounting is a very useful tool to apply to any entity including the nuclear area by calculating the use in order for the environmental passive to be zero, especially in the activity of the nuclear fuel cycle. (author)

  6. Nuclear material management: challenges and prospects

    International Nuclear Information System (INIS)

    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.)

  7. Accounting and Materialism in the History of Ideas

    OpenAIRE

    Ratnam Alagiah

    2012-01-01

    Current popular culture is connected to the birth of a secular and materialistic interpretation of reality. Materialism, which is the tendency to be more concerned with material values through rational experimentation and discourse. This paper applies Foucault’s genealogy to explain that materialism is a product of a series of historical events that are closely related to the practice of accounting. Second, accounting and “scientific materialism” have been instrumental in paving the course t...

  8. Outline of material accounting system for JNFL MOX Fuel Fabrication Plant

    International Nuclear Information System (INIS)

    JNFL MOX Fuel Fabrication Plant under construction in Rokkasho-mura Aomori Prefecture (hereinafter referred to as 'J-MOX') is a large scale commercial facility that has been designed to produce maximum 130tHM of fuel assemblies for light water reactor (BWR, PWR) per year from MOX powder to be received from JNFL Rokkasho Reprocessing Plant. Because of large amount of Plutonium to be handled at J-MOX, J-MOX plans to introduce automated facility to reduce radiation exposure for facility operator and to increase productivity. J-MOX material accounting system is designed to match with the operational method of the automated facility and to manage nuclear material on a real time basis taking into account characteristics of nuclear material. This paper presents an outline of such material accounting system. (author)

  9. British Nuclear Fuels plc: report and accounts 1987-88

    International Nuclear Information System (INIS)

    The Energy Committee has considered the report and accounts of BNFL (British Nuclear Fuels PLC) for the year 1987-88. The report looks at BNFL as a government owned PLC - its activities and financial performance. Various questions are raised about the underlying financial position justifying the optimism portrayed in the report and accounts. The impact of cost-plus contracts on UK customers is examined. The economics of THORP (Thermal Oxide Reprocessing Plant) are also examined especially as the escalation in the cost of constructing THORP means that a substantial loss will be made in the reprocessing of waste for which contracts were signed in the late 1960s or early 1970s. The main conclusions of the report are summarized. One of these is that the UK must be cautious about becoming a repository of foreign nuclear waste. Other specific recommendations are made - some about the decommissioning of BNFL plant. (UK)

  10. Advanced research workshop: nuclear materials safety

    Energy Technology Data Exchange (ETDEWEB)

    Jardine, L J; Moshkov, M M

    1999-01-28

    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

  11. Materials in Nuclear Waste Disposition

    Science.gov (United States)

    Rebak, Raul B.

    2014-03-01

    Commercial nuclear energy has been used for over 6 decades; however, to date, none of the 30+ countries with nuclear power has opened a repository for high-level waste (HLW). All countries with nuclear waste plan to dispose of it in metallic containers located in underground geologically stable repositories. Some countries also have liquid nuclear waste that needs to be reduced and vitrified before disposition. The five articles included in this topic offer a cross section of the importance of alloy selection to handle nuclear waste at the different stages of waste processing and disposal.

  12. Report of the Material Control and Material Accounting Task Force: the role of material control and material accounting in the safeguards program

    International Nuclear Information System (INIS)

    Results are presented of NRC Task Force investigations to identify the functions of a safeguards program in relation to the NRC safeguards objective, define the role and objectives of material control and material accounting systems within that program, develop goals for material control and material accounting based on those roles and objectives, assess current material control and material accounting requirements and performance levels in the light of the goals, and recommend future actions needed to attain the proposed goals. It was found that the major contribution of material accounting to the safeguards program is in support of the assurance function. It also can make secondary contributions to the prevention and response functions. In the important area of loss detection, a response measure, it is felt that limitations inherent in material accounting for some fuel cycle operations limit its ability to operate as a primary detection system to detect a five formula kilogram loss with high assurance (defined by the Task Force as a probability of detection of 90 percent or more) and that, in those cases, material accounting can act only in a backup role. Physical security and material control must make the primary contributions to the prevention and detection of theft, so that safeguards do not rely primarily for detection capabilities on material accounting. There are several areas of accounting that require more emphasis than is offered by the current regulatory base. These areas include: timely shipper-receiver difference analysis and reconciliation; a demand physical inventory capability; improved loss localization;discard measurement verification; timely recovery of scrap; improved measurement and record systems; and limits on cumulative inventory differences and shipper-receiver differences. An increased NRC capability for monitoring and analyzing licensee accounting data and more timely and detailed submittals of data to NRC by licensees are recommended

  13. The nuclear materials control technology briefing book

    Energy Technology Data Exchange (ETDEWEB)

    Hartwell, J.K.; Fernandez, S.J.

    1992-03-01

    As national and international interests in nuclear arms control and non-proliferation of nuclear weapons, intensify, it becomes ever more important that contributors be aware of the technologies available for the measurement and control of the nuclear materials important to nuclear weapons development. This briefing book presents concise, nontechnical summaries of various special nuclear material (SNM) and tritium production monitoring technologies applicable to the control of nuclear materials and their production. Since the International Atomic Energy Agency (IAEA) operates a multinational, on-site-inspector-based safeguards program in support of the Treaty on the Non-Proliferation of Nuclear Weapons (NPT), many (but not all) of the technologies reported in this document are in routine use or under development for IAEA safeguards.

  14. The Physical Protection of Nuclear Material and Nuclear Facilities

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    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

  16. Selecting and using materials for a nuclear rocket engine reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lanin, Anatolii G; Fedik, Ivan I [' Luch' Research and Production Association, Podol' sk, Moscow region (Russian Federation)

    2011-03-31

    This paper provides a historical account of how the nuclear rocket engine reactor was created and discusses the problem of selecting materials for a gas environment at a temperature of up to 3100 K and energy release of 30 MW per liter. (from the history of physics)

  17. British Nuclear Fuels PLC: report and accounts 1988-89

    International Nuclear Information System (INIS)

    This item covers a meeting held between members of the United Kingdom government's energy committee and representatives of British Nuclear Fuels (BNFL) to discuss their Annual Report and Accounts for the year 1988-89. The committee explored the reasons for escalating predictions of the costs of nuclear power and why decommissioning costs are so difficult to estimate accurately so as to include them in cost per kilowatt hour of generated electricity. The relationship between BNFL and the Ministry of Defence (MoD) was explored, as was the MoD's relationship with the United States Department of Defense. BNFL's financial position should improve when the thermal oxide reprocessing plant at Sellafield becomes operational, and the Chapelcross and Calder Hall reactors may contribute income from electricity generation. (UK)

  18. Special Nuclear Material Control by the Power Reactor Operator

    International Nuclear Information System (INIS)

    A relatively new and extremely valuable fuel for electric power production, uranium, requires very careful inventory control from the time the reactor operator assumes financial responsibility for this material until, as partially expended fuel, it is transferred to another facility and the remaining part of its initial value is recovered. Most power reactor operators were operating fossil-fuelled power plants before the advent of nuclear power and have long since established rather complete and adequate controls for these fossil fuels. The reactor operator must have no less adequate controls for the special nuclear material used in his nuclear plant. Power reactor, operation is not an ancient science and during its relatively short history our engineers and scientists have been constantly improving plant designs and methods of operation to reduce costs and make our nuclear plants competitive with fossil-fuelled conventional plants. Nuclear material management must be as modern and efficient as is humanly possible to ensure that technological advances leading to reduced costs are not lost by poor handling of nuclear fuel and the records pertaining to fuel inventory. Nuclear material management requires the maintaining of complete and informative records by the power reactor operator. These records need not be complex to satisfy the criteria of completeness and adequacy. In fact, simplicity is extremely desirable. Despite the fact that nuclear fuel is new and completely different to our conventional fuels no mystery should be attached thereto. Nuclear material control as part of nuclear material management is not limited to simple inventory work but it is the basis for a great deal of other activity that is an inherent part of any power reactor operations such as irradiated fuel shipments, reprocessing of spent fuel, with its associated accounting for reclaimed fuel and material produced during reactor operation, and the establishing and maintaining of an adequate

  19. Accounting and cost control of a nuclear power station

    International Nuclear Information System (INIS)

    1) chart or classification of accounts, 2) all plant expenses, 3) cost control, 4) storage of spare parts and supplies, 5) control of applicable dose rate, 6) charges for insurance. The accuracy of accounting and cost control is a primary thing for the efficiency in a nuclear power station. The much more important factor is the availability. It is necessary to save costs by a more effective storage or a more detailed and automatic process of single jobs in the workshop. But a very definite experience made in Obrigheim is the fact that not only commercial people know which financial loss will occur if the plant is out of operation one hour. This knowledge is also important for the technical people and for the workers in the workshops. The technical responsibility and the security in operation of the plant and the commercial understanding for the risk of non-availability do not exclude each other. (HP)

  20. Applied Nuclear Accountability Systems: A Case Study in the System Architecture and Development of NuMAC

    International Nuclear Information System (INIS)

    This is a case study of the NuMAC nuclear accountability system developed at a private fuel fabrication facility. This paper investigates nuclear material accountability and safeguards by researching expert knowledge applied in the system design and development. Presented is a system developed to detect and deter the theft of weapons grade nuclear material. Examined is the system architecture that includes: issues for the design and development of the system; stakeholder issues; how the system was built and evolved; software design, database design, and development tool considerations; security and computing ethics. (author)

  1. Aims and methods of nuclear materials management

    International Nuclear Information System (INIS)

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    Lamont, Stephen Philip [Los Alamos National Laboratory; Brisson, Marcia [DOE-IN; Curry, Michael [DEPT. OF STATE

    2011-02-17

    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

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

    International Nuclear Information System (INIS)

    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

  4. Supplier responsibility for nuclear material quality

    International Nuclear Information System (INIS)

    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

  5. Nuclear materials transportation at Battelle

    International Nuclear Information System (INIS)

    Battelle-Columbus has been a pioneer in designing and developing shipping containers for its own needs and to meet the requirements of the nuclear industry. It has participated in the design and testing of approximately 80 licensed shipping casks. Its involvement has included cask design and testing and the preparation and updating of safety analysis reports. Battelle's capabilities also include all the computer codes needed for thermal, shielding, criticality, and structural analyses as well as a drop test facility for validating codes and obtaining data to supplement structural analyses. These facilities have also been used in the design and licensing of Battelle's four shipping containers, all of which are currently in service. These casks are used principally to transport radioactive sources, surveillance capsules, and spent research reactor fuel. Battelle-Columbus designed, licensed, built, and maintains four shipping casks, primarily to support our Hot Laboratory postirradiation programs on highly irradiated structural and spent fuel materials. These casks vary in size and shipping capacities. Weights range from 1200 to 23,000 pounds. Internal cavities range from 4-1/2 in. I.D. x 5 in. deep to 15-1/2 in. I.D. x 54 in. deep. Each is licensed by the U.S. NRC for Type fissile quantities and each has an IAEA Competent Authority Permit. Although they are used primarily for own purposes, the casks are available for lease to industry and the government. Battelle-Columbus averages about 150 outgoing and incoming shipments of radioactive material a year in packages that range from 50 000 pound spent fuel casks to small 5-gallon cans. The regulatory requirements for each shipment are becoming more detailed and restrictive every day, thus each shipment can almost be considered a major project in itself. Three years ago, a truckload of radioactive waste leaving our site required the generation of only two document; now 13 internal and external documents are required. We

  6. Economic Criteria Applied to Nuclear Materials Management

    International Nuclear Information System (INIS)

    The management of nuclear materials must always be subsidiary to the primary purpose of nuclear material processing, i.e. the generation of power or the production and fabrication of end products. Therefore, those responsible for management of nuclear materials must be constantly responsive to the needs of the primary production purpose and fit the required systems to the process so as to secure the needs of nuclear materials management at optimum costs. The nuclear materials management system must concern itself with careful examination of several factors that influence its costs. The control system evolved must complement the process, providing the lowest costs of personnel, analysis and minimum interruption of the operating process. The control system should be integrated with the process needs so that quantitative information derived is available promptly to those responsible for operating supervision. The recording and reporting system should generate maximum subsidiary data. It should be compatible with the systems employed by suppliers and consumers and carry wherever possible additional information connected with the batches of nuclear material. Data generated for the control of nuclear materials should only be that needed to ensure that no significant losses, theft, misappropriation or diversion occurs. Complementary data should be subject to the same rigid test of need as that applied to the nuclear material management data. Procedures, practices, personnel and techniques have been continuously reviewed and revised to ensure the highest quality of nuclear material management performance. To ensure optimum costs balanced with adequate nuclear material control needs, some general rules have been evolved. It is all-important to determine the real needs for the recording and reporting of data. Real economies are attained by the assignment of nuclear materials management, production control and cost responsibilities to a single group. Reliance must then be

  7. Developing standard performance testing procedures for material control and accounting components at a site

    Energy Technology Data Exchange (ETDEWEB)

    Scherer, Carolynn P [Los Alamos National Laboratory; Bushlya, Anatoly V [ROSATOM, RUSSIA; Efimenko, Vladimir F [IPPE, RUSSIA; Ilyanstev, Anatoly [IPPE, RUSSIA; Regoushevsky, Victor I [IPPE, RUSSIA

    2010-01-01

    The condition of a nuclear material control and accountability system (MC&A) and its individual components, as with any system combining technical elements and documentation, may be characterized through an aggregate of values for the various parameters that determine the system's ability to perform. The MC&A system's status may be functioning effectively, marginally or not functioning based on a summary of the values of the individual parameters. This work included a review of the following subsystems, MC&A and Detecting Material Losses, and their respective elements for the material control and accountability system: (a) Elements of the MC&A Subsystem - Information subsystem (Accountancy/Inventory), Measurement subsystem, Nuclear Material Access subsystem, including tamper-indicating device (TID) program, and Automated Information-gathering subsystem; (b) Elements for Detecting Nuclear Material Loses Subsystem - Inventory Differences, Shipper/receiver Differences, Confirmatory Measurements and differences with accounting data, and TID or Seal Violations. In order to detect the absence or loss of nuclear material there must be appropriate interactions among the elements and their respective subsystems from the list above. Additionally this work includes a review of regulatory requirements for the MC&A system component characteristics and criteria that support the evaluation of the performance of the listed components. The listed components had performance testing algorithms and procedures developed that took into consideration the regulatory criteria. The developed MC&A performance-testing procedures were the basis for a Guide for MC&A Performance Testing at the material balance areas (MBAs) of State Scientific Center of the Russian Federation - Institute for Physics and Power Engineering (SSC RF-IPPE).

  8. Nuclear materials stewardship: Our enduring mission

    International Nuclear Information System (INIS)

    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

  9. Material accountancy system at a new automated mixed-oxide facility: PFPF

    International Nuclear Information System (INIS)

    At conventional mixed-oxide (MOX) fuel fabrication facilities, the personal radiation exposure of operators increases in proportion to the amount of plutonium to be handled. To resolve this issue, automated techniques in high-level radiation areas have been introduced at Japan's new MOX facility, the plutonium fuel production facility (PFPF). The PFPF incorporates a fully automated operating scheme into the main process and storage areas. Unlike conventional MOX fuel fabrication facilities, operators do not need direct access to nuclear material during normal plant operation. To achieve process control including criticality safety, PFPF has introduced an on-line computerized advanced accountancy system (AAS), which is capable of obtaining all inventory information throughout the entire facility in detail. The AAS can acquire material accounting data from equipment installed in each storage unit. All materials in the process areas are itemized as each transfer container is moved, and each container is measured at internal measurement points between a glovebox and any intermediate storage unit. The AAS can acquire material accounting data from information on the amount of nuclear material transferred. Thus, all material accounting data are obtained automatically by management on a real-time basis

  10. Nuclear Concrete Materials Database Phase I Development

    Energy Technology Data Exchange (ETDEWEB)

    Ren, Weiju [ORNL; Naus, Dan J [ORNL

    2012-05-01

    The FY 2011 accomplishments in Phase I development of the Nuclear Concrete Materials Database to support the Light Water Reactor Sustainability Program are summarized. The database has been developed using the ORNL materials database infrastructure established for the Gen IV Materials Handbook to achieve cost reduction and development efficiency. In this Phase I development, the database has been successfully designed and constructed to manage documents in the Portable Document Format generated from the Structural Materials Handbook that contains nuclear concrete materials data and related information. The completion of the Phase I database has established a solid foundation for Phase II development, in which a digital database will be designed and constructed to manage nuclear concrete materials data in various digitized formats to facilitate electronic and mathematical processing for analysis, modeling, and design applications.

  11. The Physical Protection of Nuclear Material

    International Nuclear Information System (INIS)

    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

  12. List of Nuclear Materials Licensing Actions Received

    Data.gov (United States)

    Nuclear Regulatory Commission — A catalog of all Materials Licensing Actions received for review. The catalog lists the name of the entity submitting the license application, their city and state,...

  13. Study of nuclear environment and material strategy

    International Nuclear Information System (INIS)

    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

  14. Accounting and Materialism in the History of Ideas

    Directory of Open Access Journals (Sweden)

    Ratnam Alagiah

    2012-12-01

    Full Text Available Current popular culture is connected to the birth of a secular and materialistic interpretation of reality. Materialism, which is the tendency to be more concerned with material values through rational experimentation and discourse. This paper applies Foucault’s genealogy to explain that materialism is a product of a series of historical events that are closely related to the practice of accounting. Second, accounting and “scientific materialism” have been instrumental in paving the course to their and our common failure. Third, the paper proposes a shift away from our impulse for a mere material existence leading to what has now become ‘popular culture’, to a vision of enhancing ‘an ever advancing civilization’.

  15. Overview of nuclear materials transportation

    International Nuclear Information System (INIS)

    This presentation is an overview of transportation as it relates to one specific type of material, low specific activity (LSA) material. It is the predominant type of material that fits into the low-level waste category. An attempt is made to discuss how LSA is regulated, setting forth the requirements. First the general scheme of regulations are reviewed. In addition future changes in the regulations which will affect transportation of LSA materials and, which quite likely, will have an impact on R and D needs in this area are presented

  16. Development and trial operation of a site-wide computerized material accounting system at Kurchatov Institute

    International Nuclear Information System (INIS)

    Since August 1994 Kurchatov Institute in cooperation with several US Department of Energy Laboratories has been developing a site-wide computerized material accounting system for nuclear materials. In 1994 a prototype system was put into trial operation at two Kurchatov facilities. Evaluation of this prototype led to the development of a new computerized material accounting system named KI-MACS, which has been operational since 1996. This system is a site-wide local secure computer network with centralized database capable of dealing with strictly confidential data and performing near-real time accountancy. It utilizes a Microsoft Windows NT operating system with SQL Server and Visual Basic, and has a 'star'-like network architecture. KI-MACS is capable of dealing with materials in itemized and bulk form, and can perform statistical evaluations of measurements and material balance. KI-MACS is fully integrated with bar code equipment, electronic scales, gamma-ray spectrometers and an Active Well Coincidence Counter, thus providing almost on-line evaluation and utilization of results of measurements, item identification and accounting. At present KI-MACS is being used in Physical Inventory Taking at the Kurchatov Central Storage Facility, and by the end of 1997 will be installed at twelve Kurchatov nuclear facilities

  17. Material degradation - a nuclear utility's view

    International Nuclear Information System (INIS)

    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

  18. Evaluation of Terminated Nuclear Material Licenses

    International Nuclear Information System (INIS)

    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

  19. Two-stage decision approach to material accounting

    International Nuclear Information System (INIS)

    The validity of the alarm threshold 4sigma has been checked for hypothetical large and small facilities using a two-stage decision model in which the diverter's strategic variable is the quantity diverted, and the defender's strategic variables are the alarm threshold and the effectiveness of the physical security and material control systems in the possible presence of a diverter. For large facilities, the material accounting system inherently appears not to be a particularly useful system for the deterrence of diversions, and essentially no improvement can be made by lowering the alarm threshold below 4sigma. For small facilities, reduction of the threshold to 2sigma or 3sigma is a cost effective change for the accounting system, but is probably less cost effective than making improvements in the material control and physical security systems

  20. Radiation Effects in Nuclear Waste Materials

    Energy Technology Data Exchange (ETDEWEB)

    Weber, William J.

    2005-09-30

    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.

  1. Radiation Effects in Nuclear Waste Materials

    Energy Technology Data Exchange (ETDEWEB)

    Weber, William J.

    2005-06-01

    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.

  2. Detecting errors and anomalies in computerized materials control and accountability databases

    Energy Technology Data Exchange (ETDEWEB)

    Whiteson, R.; Hench, K.; Yarbro, T. [Los Alamos National Lab., NM (United States); Baumgart, C. [Dept. of Energy, Albuquerque, NM (United States). Kansas City Plant

    1998-12-31

    The Automated MC and A Database Assessment project is aimed at improving anomaly and error detection in materials control and accountability (MC and A) databases and increasing confidence in the data that they contain. Anomalous data resulting in poor categorization of nuclear material inventories greatly reduces the value of the database information to users. Therefore it is essential that MC and A data be assessed periodically for anomalies or errors. Anomaly detection can identify errors in databases and thus provide assurance of the integrity of data. An expert system has been developed at Los Alamos National Laboratory that examines these large databases for anomalous or erroneous data. For several years, MC and A subject matter experts at Los Alamos have been using this automated system to examine the large amounts of accountability data that the Los Alamos Plutonium Facility generates. These data are collected and managed by the Material Accountability and Safeguards System, a near-real-time computerized nuclear material accountability and safeguards system. This year they have expanded the user base, customizing the anomaly detector for the varying requirements of different groups of users. This paper describes the progress in customizing the expert systems to the needs of the users of the data and reports on their results.

  3. Identifying Nuclear Materials Using Tagged Muons

    CERN Document Server

    Morris, C L; Borodzin, K; Durham, J M; Fabritius, J M; Guardincerri, E; Hecht, A; Milner, E C; Miyadera, H; Perry, J O; Poulson, D

    2014-01-01

    Experimental results from a new technique that uses neutrons generated by stopped cosmic-ray muons to identify nuclear materials are described. The neutrons are used to tag muon-induced fission events in actinides and laminography is used to form images of the stopping material. This technique allows the imaging of uranium objects tagged using muon tracking detectors located above or to the side of the objects. The specificity of the technique to significant quantities of nuclear material along with its insensitivity to spatial details may provide a new method for the task of warhead verification for future arms reduction treaties.

  4. The Management of Nuclear Materials in a Research Establishment

    International Nuclear Information System (INIS)

    The functions of a nuclear materials management scheme are reviewed in relation to the activities of research establishments. Since these activities are normally non-repetitive, there is little opportunity to establish statistical quality and quantity control. The risks of an error in the material accounts must therefore be established from relatively few analytical measurements and the implications of this are discussed. Similar arguments are applied to illustrate the difficulties of quality control on suppliers when a large variety of materials are being purchased in small quantities. (author)

  5. Progress in the activities on prevention and combating of illicit trafficking of nuclear material in Lithuania

    International Nuclear Information System (INIS)

    The paper gives a general overview of the progress, which has been done in the activities on prevention and combating of illicit trafficking of nuclear material in Lithuania. It describes the measures, which were taken to strengthen nuclear material accounting and control and physical protection. The current status of the national legislation and the functions of institutions involved in control of nuclear material and combating of illicit trafficking are discussed. (author)

  6. Passive nondestructive assay of nuclear materials

    International Nuclear Information System (INIS)

    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

  7. 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)

  8. Materials Control System for Enriched Uranium Chemical Processing Facility for Irradiated Nuclear Materials

    International Nuclear Information System (INIS)

    Systems for management and control of nuclear material in an enriched uranium chemical processing facility are not too different from those historically used in the chemical industry. The difference is one of degree rather than substance. The monetary and strategic value of the material being processed as well as the potential health and safety hazards inherent in handling nuclear material often dictate a level of effort and system detail above that which might seem reasonable to the casual observer. Among those areas of consideration which are of particular importance in the development of an effective nuclear materials management (NMM) system as based on experience gained at the Idaho Chemical Processing Plant are the following: organizational structure, accounting system, measurement system, implementation and integration of system, records and reports, internal audit, and inventory management. (author)

  9. Materials analysis with a nuclear microprobe

    International Nuclear Information System (INIS)

    The ability to produce focused beams of a few MeV light ions from Van de Graaff accelerators has resulted in the development of nuclear microprobes. Rutherford backscattering, nuclear reactions, and particle-induced x-ray emission are used to provide spatially resolved information from the near surface region of materials. Rutherford backscattering provides nondestructive depth and mass resolution. Nuclear reactions are sensitive to light elements (Z < 15). Particle-induced x-ray analysis is similar to electron microprobe analysis, but 2 orders of magnitude more sensitive. The focused beams are usually produced with specially designed multiplets of magnetic quadrupoles. The LASL microprobe uses a superconducting solenoid as a final lens. The data are acquired by a computer interfaced to the experiment with CAMAC. The characteristics of the information acquired with a nuclear microprobe are discussed; the means of producing the beams of nuclear particles are described; and the limitations and applications of such systems are given

  10. Preliminary concepts for materials measurement and accounting in critical facilities

    International Nuclear Information System (INIS)

    Preliminary concepts are presented for improved materials measurement and accounting in large critical facilities. These concepts will be developed as part of a study that will emphasize international safeguarding of critical facilities. The major safeguards problem is the timely verification of in-reactor inventory during periods of reactor operation. This will require a combination of measurement, statistical sampling, and data analysis techniques. Promising techniques include integral measurements of reactivity and other reactor parameters that are sensitive to the total fissile inventory, and nondestructive assay measurements of the fissile material in reactor fuel drawers and vault storage canisters coupled with statistical sampling plans tailored for the specific application. The effectiveness of proposed measurement and accounting strategies will be evaluated during the study

  11. Robust topology optimization accounting for misplacement of material

    DEFF Research Database (Denmark)

    Jansen, Miche; Lombaert, Geert; Diehl, Moritz;

    2013-01-01

    . The random field is conditioned in order to incorporate supports in the design where no misplacement of material occurs. In the robust optimization problem, the objective function is defined as a weighted sum of the mean value and the standard deviation of the performance of the structure under uncertainty...... into account this type of geometric imperfections. A density filter based approach is followed, and translations of material are obtained by adding a small perturbation to the center of the filter kernel. The spatial variation of the geometric imperfections is modeled by means of a vector valued random field...

  12. Decision-directed materials-accounting procedures: an overview

    International Nuclear Information System (INIS)

    With materials balances taken at intervals, methods for treating materials balance data and their use by safeguards decision-making are relatively straightforward. The emphasis on accounting in which balances may be drawn on a daily or weekly basis, raises anew questions in these two areas: (1) what is the most effective means of extracting the maximum amount of information; and (2) how should safeguards decision-makers use the results, and what impact does the decision process have on the analysis techniques. These questions lead to considering combinations of materials balances, which exposes a whole new set of concerns. For example, we must select the most appropriate combinations, which implies some consideration of possible diversion scenarios, such as abrupt or protracted. Control of the overall false-alarm rate is an important requisite of the composite procedure. Significant work has been done on loss estimators, but their role in the materials accounting decision process has only begun to be examined. Current criteria may require periodic statements with respect to materials loss; the analysis procedures must be structured to provide such information. This paper presents an overview of the current technology. Questions still to be answered are pointed out

  13. Nuclear wasteform materials: Atomistic simulation case studies

    Energy Technology Data Exchange (ETDEWEB)

    Chroneos, A., E-mail: alex.chroneos@open.ac.uk [Materials Engineering, The Open University, Milton Keynes MK7 6AA (United Kingdom); Department of Materials, Imperial College London, London SW7 2AZ (United Kingdom); Institute of Materials Science, NCSR Demokritos, GR-15310 Athens (Greece); Rushton, M.J.D. [Department of Materials, Imperial College London, London SW7 2AZ (United Kingdom); Jiang, C. [State Key Laboratory of Powder Metallurgy, Central South University, Changsha 410083 (China); Tsoukalas, L.H. [Department of Nuclear Engineering, Purdue University, West Lafayette, IN 47907 (United States)

    2013-10-15

    Ever increasing global energy demand combined with a requirement to reduce CO{sub 2} emissions has rekindled an interest in nuclear power generation. In order that nuclear energy remains publicly acceptable and therefore a sustainable source of power it is important that nuclear waste is dealt with in a responsible manner. To achieve this, improved materials for the long-term immobilisation of waste should be developed. The extreme conditions experienced by nuclear wasteforms necessitate the detailed understanding of their properties and the mechanisms acting within them at the atomic scale. This latter issue is the focus of the present review. Atomic scale simulation techniques can accelerate the development of new materials for nuclear wasteform applications and provide detailed information on their physical properties that cannot be easily accessed by experiment. The present article introduces examples of how atomic scale, computational modelling techniques have led to an improved understanding of current nuclear wasteform materials and also suggest how they may be used in the development of new wasteforms.

  14. Radiation Effects in Nuclear Waste Materials

    Energy Technology Data Exchange (ETDEWEB)

    Weber, William J.; Corrales, L. Rene; Ness, Nancy J.; Williford, Ralph E.; Heinisch, Howard L.; Thevuthasan, Suntharampillai; Icenhower, Jonathan P.; McGrail, B. Peter; Devanathan, Ramaswami; Van Ginhoven, Renee M.; Song, Jakyoung; Park, Byeongwon; Jiang, Weilin; Begg, Bruce D.; Birtcher, R. B.; Chen, X.; Conradson, Steven D.

    2000-10-02

    Radiation effects from the decay of radionuclides may impact the long-term performance and stability of nuclear waste forms and stabilized nuclear materials. In an effort to address these concerns, the objective of this project was the development of fundamental understanding of radiation effects in glasses and ceramics, particularly on solid-state radiation effects and their influence on aqueous dissolution kinetics. This study has employed experimental, theoretical and computer simulation methods to obtain new results and insights into radiation damage processes and to initiate the development of predictive models. Consequently, the research that has been performed under this project has significant implications for the High-Level Waste and Nuclear Materials focus areas within the current DOE/EM mission. In the High-Level Waste (HLW) focus area, the results of this research could lead to improvements in the 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 focus area, the results of this research could 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. Ultimately, this research could 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.

  15. Development of Nuclear Materials and Degradation Database

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Ho Sang [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of); Park, Heung Bae [KEPCO Engineering and Construction Company, Seongnam (Korea, Republic of)

    2010-10-15

    There are about 440 operating nuclear power reactors in the world including 20 units from Korea. The average age of the reactors is more than 20 years and many of them are approaching to their original 30 or 40 years licensing terms. Even though some failures were reported in components or pipes of nuclear power plants (NPPs), these NPPs are considered to be too valuable to stop their operation at the end of design life. Therefore, the long-term operation of NPPs has become a worldwide trend based on technical and economic consideration. In order to ensure safe long-term operation of NPPs, it is increasingly necessary to adopt new approaches to deal with nuclear materials aging and degradation. Proactive Material Degradation Assessment (PMDA) is one of the key elements of these new approaches. Many kinds of background information such as materials and degradation history of components or piping in NPP plant are also needed for PMDA by the experts. Nuclear Materials and Degradation Database is being developed as a part of Nuclear Technology Revolution Project (NTRP) funded by the Ministry of Knowledge Economy (MKE)

  16. Technologies for detection of nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    DeVolpi, A.

    1996-03-30

    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.

  17. Agreement of 13 December 1991 between the Republic of Argentina, the Federative Republic of Brazil, the Brazilian-Argentine agency for accounting and control of nuclear materials and the International Atomic Energy Agency for the application of safeguards

    International Nuclear Information System (INIS)

    The document reproduces the text of an agreement by exchange of letters with the Argentine Republic in connection with the Treaty on the Non-Proliferation of Nuclear Weapons and the Treaty for the Prohibition of Nuclear Weapons in Latin America and the Caribbean. The agreement was approved by the Board of Governors on 18 March 1997 and entered into force on that date

  18. Toward better management of nuclear materials in Japan and Asia

    International Nuclear Information System (INIS)

    The Asian region is drawing a great deal of attention from all over the world regarding its possible future role as the core of worldwide peaceful nuclear energy development. Northeast Asia, Japan, Korea, and Taiwan already have a significant amount of nuclear power generation. Furthermore, these countries together with China have expansion plans. Southeast Asia is just beginning to plan and construct civilian nuclear power stations. Among these Asian countries, Japan can be regarded as one of the most developed nations as far as peaceful nuclear energy is concerned. Within Japan several nuclear fuel cycle facilities, including reprocessing and uranium enrichment facilities, are in operation. Research and developmental activities on fast breeder reactors are continuing. On this occasion the author explains three topics in general. The first is the history and the present situation of Japanese nuclear energy development and nuclear materials management. The second topic is Japan's efforts to strengthen international nonproliferation efforts, which include: various assistances in the dismantling of the former Soviet Union's nuclear forces; Japan's participation in the Korean Peninsula Energy Development Organization (KEDO), which is responsible for the supply of two light water reactors to the Democratic people's Republic of Korea (DPRK); Japan's initiative and contributions to the establishment of guidelines for use and storage of separated plutonium; technical and financial support to the IAEA safeguards implementation; and the strengthening of the Japanese system of accounting for and control of nuclear materials (SSAC) in connection with the Agency's activity, Program 93+2. The last topic addresses is concerned with nuclear energy in the Asian region. The concept of ASIATOM, or PACIFIC ATOM is now being widely discussed in several countries in Asia. The author discusses this idea, especially regarding the objectives, possible contents and the structures

  19. Comparison of materials accounting in conversion and coconversion processes

    International Nuclear Information System (INIS)

    Materials accounting systems performances are compared for plutonium nitrate-to-oxide conversion [Oxalate (III)] and uranium-plutonium coconversion (Coprecal and modified Coprecal). These processes have the same design basis plutonium throughput and achieve this throughput in parallel operating lines. However, the process line configurations differ. In comparing the materials loss detection sensitivities for the three processes, we find better materials loss detection sensitivity for the Oxalate (III) process than for either of the two Coprecal processes, better single-balance detection sensitivity for the original Coprecal than for the modified Coprecal, and better long-term detection sensitivity (> 1d) for the modified Coprecal than for the original Coprecal. Sensivity differences result from differences in in-process inventories, feeding arrangements, and scrap generation

  20. Technology development of nuclear material safeguards for DUPIC fuel cycle

    International Nuclear Information System (INIS)

    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

  1. Design of standards for nondestructive assay of special nuclear material

    Energy Technology Data Exchange (ETDEWEB)

    Smith, H.A. Jr.; Stewart, J.E. [Los Alamos National Lab., NM (United States); Ruhter W. [Lawrence Livermore National Lab., CA (United States)

    1997-05-01

    Nondestructive assay (NDA) of special nuclear material (SNM) involves a variety of measurement techniques, instruments, and nuclear materials. High-quality measurements require well-characterized SNM standards that represent the expected range of mass, chemical composition, and physical properties of the SNM to be measured. Due to the very limited commercial availability of NDA standards, facilities must usually produce their own standards, both to meet their specific measurement needs and to comply with existing regulations. This paper will describe the current extent to which NDA standards are commercially available. The authors will further describe the types of NDA standards used to calibrate and verify the measurement techniques commonly used in the safeguards of SNM. Several types of NDA standards will be discussed in detail to illustrate the considerations that go into specifying and designing traceable, representative standards for materials accounting measurements.

  2. 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.

  3. Agreement of 13 December 1991 between the Republic of Argentina, the Federative Republic of Brazil, the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials and the International Atomic Energy Agency for the application of safeguards

    International Nuclear Information System (INIS)

    The document reproduces the text of the Exchange of Letters concerning an agreement with the Federative Republic of Brazil in connection with the Treaty on the Non-Proliferation of Nuclear Weapons and the Treaty for the Prohibition of Nuclear Weapons in Latin America and the Caribbean. The agreement reflected in the Exchange of Letters was approved by the Board of Governors on 20 September 1999, and entered into force on that date

  4. National and international nuclear material monitoring

    International Nuclear Information System (INIS)

    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

  5. Muon Tracking to Detect Special Nuclear Materials

    Energy Technology Data Exchange (ETDEWEB)

    Schwellenbach, D. [NSTec; Dreesen, W. [NSTec; Green, J. A. [NSTec; Tibbitts, A. [NSTec; Schotik, G. [NSTec; Borozdin, K. [LANL; Bacon, J. [LANL; Midera, H. [LANL; Milner, C. [LANL; Morris, C. [LANL; Perry, J. [LANL; Barrett, S. [UW; Perry, K. [UW; Scott, A. [UW; Wright, C. [UW; Aberle, D. [NSTec

    2013-03-18

    Previous experiments have proven that nuclear assemblies can be imaged and identified inside of shipping containers using vertical trajectory cosmic-ray muons with two-sided imaging. These experiments have further demonstrated that nuclear assemblies can be identified by detecting fission products in coincidence with tracked muons. By developing these technologies, advanced sensors can be designed for a variety of warhead monitoring and detection applications. The focus of this project is to develop tomographic-mode imaging using near-horizontal trajectory muons in conjunction with secondary particle detectors. This will allow imaging in-situ without the need to relocate the objects and will enable differentiation of special nuclear material (SNM) from other high-Z materials.

  6. Designed porosity materials in nuclear reactor components

    Energy Technology Data Exchange (ETDEWEB)

    Yacout, A. M.; Pellin, Michael J.; Stan, Marius

    2016-09-06

    A nuclear fuel pellet with a porous substrate, such as a carbon or tungsten aerogel, on which at least one layer of a fuel containing material is deposited via atomic layer deposition, and wherein the layer deposition is controlled to prevent agglomeration of defects. Further, a method of fabricating a nuclear fuel pellet, wherein the method features the steps of selecting a porous substrate, depositing at least one layer of a fuel containing material, and terminating the deposition when the desired porosity is achieved. Also provided is a nuclear reactor fuel cladding made of a porous substrate, such as silicon carbide aerogel or silicon carbide cloth, upon which layers of silicon carbide are deposited.

  7. Nuclear Materials Identification System Operational Manual

    Energy Technology Data Exchange (ETDEWEB)

    Chiang, L.G.

    2001-04-10

    This report describes the operation and setup of the Nuclear Materials Identification System (NMIS) with a {sup 252}Cf neutron source at the Oak Ridge Y-12 Plant. The components of the system are described with a description of the setup of the system along with an overview of the NMIS measurements for scanning, calibration, and confirmation of inventory items.

  8. 10 CFR 74.15 - Nuclear material transaction reports.

    Science.gov (United States)

    2010-01-01

    ... for transfers and receipts, shall submit a Nuclear Material Transaction Report, in computer-readable.... Each licensee who transfers the material shall submit a Nuclear Material Transaction Report in computer.... Each licensee who receives the material shall submit a Nuclear Material Transaction Report in...

  9. Retrieval system of nuclear data for transmutation of nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Fujita, Mitsutane; Utsumi, Misako; Noda, Tetsuji [National Research Inst. for Metals, Tsukuba, Ibaraki (Japan)

    1997-03-01

    A database storing the data on nuclear reaction was built to calculate for simulating transmutation behaviours of materials /1/-/3/. In order to retrieve and maintain the database, the user interface for the data retrieval was developed where special knowledge on handling of the database or the machine structure is not required for end-user. It is indicated that using the database, the possibility of He formation and radioactivity in a material can be easily retrieved though the evaluation is qualitatively. (author)

  10. Nuclear Materials: Reconsidering Wastes and Assets - 13193

    International Nuclear Information System (INIS)

    The nuclear industry, both in the commercial and the government sectors, has generated large quantities of material that span the spectrum of usefulness, from highly valuable ('assets') to worthless ('wastes'). In many cases, the decision parameters are clear. Transuranic waste and high level waste, for example, have no value, and is either in a final disposition path today, or - in the case of high level waste - awaiting a policy decision about final disposition. Other materials, though discardable, have intrinsic scientific or market value that may be hidden by the complexity, hazard, or cost of recovery. An informed decision process should acknowledge the asset value, or lack of value, of the complete inventory of materials, and the structure necessary to implement the range of possible options. It is important that informed decisions are made about the asset value for the variety of nuclear materials available. For example, there is a significant quantity of spent fuel available for recycle (an estimated $4 billion value in the Savannah River Site's (SRS) L area alone); in fact, SRS has already blended down more than 300 metric tons of uranium for commercial reactor use. Over 34 metric tons of surplus plutonium is also on a path to be used as commercial fuel. There are other radiological materials that are routinely handled at the site in large quantities that should be viewed as strategically important and / or commercially viable. In some cases, these materials are irreplaceable domestically, and failure to consider their recovery could jeopardize our technological leadership or national defense. The inventories of nuclear materials at SRS that have been characterized as 'waste' include isotopes of plutonium, uranium, americium, and helium. Although planning has been performed to establish the technical and regulatory bases for their discard and disposal, recovery of these materials is both economically attractive and in the national interest. (authors)

  11. US/Russian program in materials protection, control and accounting at the RRC Kurchatov Institute: 1997--1998

    International Nuclear Information System (INIS)

    Six US Department of Energy Laboratories are carrying out a program of cooperation with the Russian Research Center Kurchatov Institute to improve nuclear material protection, control and accounting (MPC and A) at Kurchatov. In 1997--1998 the primary thrust of this program has been directed to Building 106, which houses a number of test reactors and critical facilities. Substantial improvements in physical protection, upgrades in the physical inventory taking procedures, installation of equipment for the computerized materials accounting system, and installation of nuclear material portal monitors and neutron-based measurement equipment are being carried out at this facility. Software for the computerized accounting system, named KI-MACS, has been developed at Kurchatov and the system has been fully integrated with the bar code printing and reading equipment, electronic scales, and nondestructive assay equipment provided under this program. Additional 1997--1998 activities at Kurchatov include continuation of a tamper indicating device program, vulnerability assessments of several facilities, hosting of a Russian-American Workshop on Fissile Material Control and Accountability at Critical Facilities, and the development of accounting procedures for transfers of nuclear materials between material balance areas

  12. Regional material flow accounting and environmental pressures: the Spanish case.

    Science.gov (United States)

    Sastre, Sergio; Carpintero, Óscar; Lomas, Pedro L

    2015-02-17

    This paper explores potential contributions of regional material flow accounting to the characterization of environmental pressures. With this aim, patterns of material extraction, trade, consumption, and productivity for the Spanish regions were studied within the 1996-2010 period. The main methodological variation as compared to whole-country based approaches is the inclusion of interregional trade, which can be separately assessed from the international exchanges. Each region was additionally profiled regarding its commercial exchanges with the rest of the regions and the rest of the world and the related environmental pressures. Given its magnitude, interregional trade is a significant source of environmental pressure. Most of the exchanges occur across regions and different extractive and trading patterns also arise at this scale. These differences are particularly great for construction minerals, which in Spain represent the largest share of extracted and consumed materials but do not cover long distances, so their impact is visible mainly at the regional level. During the housing bubble, economic growth did not improve material productivity.

  13. Development of property management system for nuclear material

    International Nuclear Information System (INIS)

    In the past, the ownership of nuclear material was transferred to PNC from electric power companies at TRP. So, it was unnecessary for PCDF to manage this ownership of nuclear material especially. However, at present, the ownership of nuclear material is transferred to PNC sometime after PCDF finish converting nitrate solution into MOX powder. Moreover, there exist some MOX powder which maintains its former ownership even after conversion, and thus exist some material consist of Pu which does not belongs to PNC and U which belongs to PNC. Therefore, necessity of providing special management arose. In order to provide an adequate management, we have developed the system which interprets established ownership of Pu nitrate solution in each receipt batch from TRP into allocated ownership of converted powder in each can at PCDF automatically. This interpretation is supported by the use of information of inventory change from material accountancy system. In this presentation, outline of the system and the concept of the allocation of ownership is reported. (author)

  14. Materials for generation-IV nuclear reactors

    International Nuclear Information System (INIS)

    Materials science and materials development are key issues for the implementation of innovative reactor systems such as those defined in the framework of the Generation IV. Six systems have been selected for Generation IV consideration: gas-cooled fast reactor, lead-cooled fast reactor, molten salt-cooled reactor, sodium-cooled fast reactor, supercritical water-cooled reactor, and very high temperature reactor. The structural materials need to resist much higher temperatures, higher neutron doses and extremely corrosive environment, which are beyond the experience of the current nuclear power plants. For this reason, the first consideration in the development of Generation-IV concepts is selection and deployment of materials that operate successfully in the aggressive operating environments expected in the Gen-IV concepts. This paper summarizes the Gen-IV operating environments and describes the various candidate materials under consideration for use in different structural applications. (author)

  15. Nuclear archaeology: Verifying declarations of fissile-material production

    International Nuclear Information System (INIS)

    Controlling the production of fissile material is an essential element of nonproliferation policy. Similarly, accounting for the past production of fissile material should be an important component of nuclear disarmament. This paper describes two promising techniques that make use of physical evidence at reactors and enrichment facilities to verify the past production of plutonium and highly enriched uranium. In the first technique, the concentrations of long-lived radionuclides in permanent components of the reactor core are used to estimate the neutron fluence in various regions of the reactor, and thereby verify declarations of plutonium production in the reactor. In the second technique, the ratio of the concentration of U-235 to that of U-234 in the tails is used to determine whether a given container of tails was used in the production of low- enriched uranium, which is suitable for reactor fuel, or highly enriched uranium, which can be used in nuclear weapons. Both techniques belong to the new field of open-quotes nuclear archaeology,close quotes in which the authors attempt to document past nuclear weapons activities and thereby lay a firm foundation for verifiable nuclear disarmament. 11 refs., 1 fig., 3 tabs

  16. Material protection control and accounting program activities at the Urals electrochemical integrated plant

    International Nuclear Information System (INIS)

    The Urals Electrochemical Integrated Plant (UEIP) is the Russian Federation's largest uranium enrichment plant and one of three sites in Russia blending high enriched uranium (HEU) into commercial grade low enriched uranium. UEIP is located approximately 70 km north of Yekaterinburg in the closed city of Novouralsk (formerly Sverdlovsk- 44). DOE's MPC ampersand A program first met with UEIP in June of 1996, however because of some contractual issues the work did not start until September of 1997. The six national laboratories participating in DOE's Material Protection Control and Accounting program are cooperating with UEIP to enhance the capabilities of the physical protection, access control, and nuclear material control and accounting systems. The MPC ampersand A work at UEIP is expected to be completed during fiscal year 2001

  17. Nuclear Resonance Fluorescence for Materials Assay

    International Nuclear Information System (INIS)

    This paper discusses the use of nuclear resonance fluorescence (NRF) techniques for the isotopic and quantitative assaying of radioactive material. Potential applications include age-dating of an unknown radioactive source, pre- and post-detonation nuclear forensics, and safeguards for nuclear fuel cycles Examples of age-dating a strong radioactive source and assaying a spent fuel pin are discussed. The modeling work has been performed with the Monte Carlo radiation transport computer code MCNPX, and the capability to simulate NRF has bee added to the code. Discussed are the limitations in MCNPX?s photon transport physics for accurately describing photon scattering processes that are important contributions to the background and impact the applicability of the NRF assay technique.

  18. Nondestructive analysis of nuclear materials by isotopic source assay system

    International Nuclear Information System (INIS)

    Destructive assay is an effective method for the analysis of nuclear materials in nuclear fuels, but is not suitable for some aspects of nuclear fuel cycle, for example, for accounting and control or safeguard purposes. Isotopic Source Assay System was imported from Intelcom Rad. Tech. Company, and the results of assay of enriched uranium and plutonium sealed for passive and active assay by the system are presented. A 252Cf source is provided for the assay system. Assay of unknown samples by this system is carried out relatively to the measurement of known standards. Several known standards approximating the physical and chemical properties of unknown samples are prepared to make calibration curves. When one fission event occurs in a sample, a few neutrons (2.5 neutrons on the average) and gamma ray (about 7 photons) are emitted simultaneously. By three detector coincidence out of four, one count is registered by the assay system. First, statistical informations and geometry were examined. Then, three kinds of enriched uranium were measured to examine the measurement on 238U. Passive and active measurements were performed on 4.32 grams of PuO2 during one month to know reproducibility. In conclusion of these tests, it was proved to be able to apply this system to the analysis of nuclear materials similar in enrichment or isotopic composition, and scraps and wastes containing known matrix materials. (Wakatsuki, Y.)

  19. Physical protection of nuclear material in the nuclear powered icebreaker fleet in Murmansk

    International Nuclear Information System (INIS)

    A total of eight nuclear powered ships, owned by the Russian Ministry of Transportation (MINTRAN) and operated by the Murmansk Shipping Company (MSCo), constitute the Russian nuclear icebreaker fleet, supporting the northern Arctic shipping routes. The ships are five seagoing icebreakers, two river icebreakers and one freighter. The reactors in the vessels are based on the same design as reactors in submarines, using highly enriched uranium fuel. The present security standards for the fuel are not satisfactory. Given the lack of permanent on-shore storage facilities, fresh and spent fuel is stored on two ships lying at the dockside together with the icebreaker fleet at the 'RTP Atomflot', a harbour approximately two kilometers north of the centre of Murmansk. While the fresh highly enriched uranium fuel poses a serious proliferation risk, the spent fuel mainly represents a potential pollution risk. Upgrading of the physical protection at the MSCo will bring all nuclear material under high level security in the next few years. Key targets for physical protection are the port area, the storage ships 'Imandra' and 'Lotta' because of the nuclear material contained on these ships, and the improved physical protection of the reactor sections on the icebreakers. The Norwegian Radiation Protection Authority and the Swedish Nuclear Power Inspectorate have agreed with Gosatomnadzor of Russia and the MSCo to support the Company to further improve the physical protection system on the ships in the Atomic Fleet, as well as the system of accountancy and control of their nuclear fuel. (author)

  20. The physical protection of nuclear material

    International Nuclear Information System (INIS)

    Technical Committee met 21-25 June 1993 to consider changes to INFCIRC/225/Rev.2. The revised document, INFCIRC/225/Rev.3, reflects the Technical Committee recommendations for changes to the text as well as other modifications determined necessary to advance the consistency of the Categorization Table in INFCIRC/225/Rev.2 with the categorization table contained in The Convention of the Physical Protection of Nuclear Material and to reflect additional improvements presented by the experts. 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

  1. Nuclear Fuels & Materials Spotlight Volume 4

    Energy Technology Data Exchange (ETDEWEB)

    I. J. van Rooyen,; T. M. Lillo; Y. Q. WU; P.A. Demkowicz; L. Scott; D.M. Scates; E. L. Reber; J. H. Jackson; J. A. Smith; D.L. Cottle; B.H. Rabin; M.R. Tonks; S.B. Biner; Y. Zhang; R.L. Williamson; S.R. Novascone; B.W. Spencer; J.D. Hales; D.R. Gaston; C.J. Permann; D. Anders; S.L. Hayes; P.C. Millett; D. Andersson; C. Stanek; R. Ali; S.L. Garrett; J.E. Daw; J.L. Rempe; J. Palmer; B. Tittmann; B. Reinhardt; G. Kohse; P. Ramuhali; H.T. Chien; T. Unruh; B.M. Chase; D.W. Nigg; G. Imel; J. T. Harris

    2014-04-01

    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: • The first identification of silver and palladium migrating through the SiC layer in TRISO fuel • A description of irradiation assisted stress corrosion testing capabilities that support commercial light water reactor life extension • Results of high-temperature safety testing on coated particle fuels irradiated in the ATR • New methods for testing the integrity of irradiated plate-type reactor fuel • Description of a 'Smart Fuel' concept that wirelessly provides real time information about changes in nuclear fuel properties and operating conditions • Development and testing of ultrasonic transducers and real-time flux sensors for use inside reactor cores, and • An example of a capsule irradiation test. 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 to spur innovation in nuclear energy applications that drive economic growth and energy security. We appreciate your interest in our work here at INL, and hope that you find this issue informative.

  2. Molecular forensic science analysis of nuclear materials

    Science.gov (United States)

    Reilly, Dallas David

    Concerns over the proliferation and instances of nuclear material in the environment have increased interest in the expansion of nuclear forensics analysis and attribution programs. A new related field, molecular forensic science (MFS) has helped meet this expansion by applying common scientific analyses to nuclear forensics scenarios. In this work, MFS was applied to three scenarios related to nuclear forensics analysis. In the first, uranium dioxide was synthesized and aged at four sets of static environmental conditions and studied for changes in chemical speciation. The second highlighted the importance of bulk versus particle characterizations by analyzing a heterogeneous industrially prepared sample with similar techniques. In the third, mixed uranium/plutonium hot particles were collected from the McGuire Air Force Base BOMARC Site and analyzed for chemical speciation and elemental surface composition. This work has identified new signatures and has indicated unexpected chemical behavior under various conditions. These findings have lead to an expansion of basic actinide understanding, proof of MFS as a tool for nuclear forensic science, and new areas for expansion in these fields.

  3. Radioactive materials released from nuclear power plants

    International Nuclear Information System (INIS)

    Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1987 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1987 release data are summarized in tabular form. Data covering specific radionuclides are summarized. 16 tabs

  4. Nuclear data needs for material analysis

    International Nuclear Information System (INIS)

    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)

  5. Contributions to radiochemical and nuclear materials research

    International Nuclear Information System (INIS)

    Series of talks given during a seminar of the European Institute for Transuranium Elements in april 1981 in honor of R. LINDNER on the occasion of his 60th birth day. The topics include general aspects of research practice and science prognosis, retrospective essays about the discovery of nuclear fission by O. HAHN as well as surveys of actual research activities concerning a radiochemistry and the use of radioactivity in material science

  6. Nuclear physics methods in materials research

    International Nuclear Information System (INIS)

    The brochure contains the abstracts of the papers presented at the 7th EPS meeting 1980 in Darmstadt. The main subjects were: a) Neutron scattering and Moessbauer effect in materials research, b) ion implantation in micrometallurgy, c) applications of nuclear reactions and radioisotopes in research on solids, d) recent developments in activation analysis and e) pions, positrons, and heavy ions applied in solid state physics. (RW)

  7. Radioactive materials released from nuclear power plants

    International Nuclear Information System (INIS)

    Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1991 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1991 release data are summarized in tabular form. Data Covering specific radionuclides are summarized

  8. Institutional issues affecting transportation of nuclear materials

    International Nuclear Information System (INIS)

    The institutional issues affecting transportation of nuclear materials in the United States represent significant barriers to meeting future needs in the transport of radioactive waste materials to their ultimate repository. While technological problems which must be overcome to perform such movements seem to be within the state-of-the-art, the timely resolution of these institutional issues seems less assured. However, the definition of these issues, as attempted in this paper, together with systematic analysis of cause and possible solutions are the essential elements of the Transportation Technology Center's Institutional Issues Program

  9. Nuclear reactor materials at the atomic scale

    Directory of Open Access Journals (Sweden)

    Emmanuelle A. Marquis

    2009-11-01

    Full Text Available With the renewed interest in nuclear energy, developing new materials able to respond to the stringent requirements of the next-generation fission and future fusion reactors has become a priority. An efficient search for such materials requires detailed knowledge of material behaviour under irradiation, high temperatures and corrosive environments. Minimizing the rates of materials degradation will be possible only if the mechanisms by which it occurs are understood. Atomic-scale experimental probing as well as modelling can provide some answers and help predict in-service behaviour. This article illustrates how this approach has already improved our understanding of precipitation under irradiation, corrosion behaviour, and stress corrosion cracking. It is also now beginning to provide guidance for the development of new alloys.

  10. Materials qualification for nuclear power plants

    International Nuclear Information System (INIS)

    The supply of materials to be used in the fabrication of components submitted to pressure destined to Atucha II nuclear power plant must fulfill the quality assurance requirements in accordance with the international standards. With the aim of promoting the national participation in CNA II, ENACE had the need to adapt these requirements to the national industry conditions and to the availability of official entities' qualification and inspection. As a uniform and normalized assessment for the qualification of materials did not exist in the country, ENACE had to develop a materials suppliers qualification system. This paper presents a suppliers qualification procedure, its application limits and the alternative procedures for the acceptance of individual stock and for the stock materials purchase. (Author)

  11. Integrating the stabilization of nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Dalton, H.F. [Department of Energy, Washington, DC (United States)

    1996-05-01

    In response to Recommendation 94-1 of the Defense Nuclear Facilities Safety Board, the Department of Energy committed to stabilizing specific nuclear materials within 3 and 8 years. These efforts are underway. The Department has already repackaged the plutonium at Rocky Flats and metal turnings at Savannah River that had been in contact with plastic. As this effort proceeds, we begin to look at activities beyond stabilization and prepare for the final disposition of these materials. To describe the plutonium materials being stabilize, Figure 1 illustrates the quantities of plutonium in various forms that will be stabilized. Plutonium as metal comprises 8.5 metric tons. Plutonium oxide contains 5.5 metric tons of plutonium. Plutonium residues and solutions, together, contain 7 metric tons of plutonium. Figure 2 shows the quantity of plutonium-bearing material in these four categories. In this depiction, 200 metric tons of plutonium residues and 400 metric tons of solutions containing plutonium constitute most of the material in the stabilization program. So, it is not surprising that much of the work in stabilization is directed toward the residues and solutions, even though they contain less of the plutonium.

  12. Quality assurance and quality control at the joint IAEA NMCC On-Site Laboratory at RRP as a contribution to the inspectorate's review of near real time accountancy of nuclear material

    International Nuclear Information System (INIS)

    This paper provides updates on the elements of the quality management system (QMS) of the On-Site Laboratory for nuclear safeguards at the Rokkasho Reprocessing Plant. Representative examples of the OSL's quality control levels are discussed, such as analytical method performance review, method inter-comparison and participation in Laboratory inter-comparison exercises. It also highlights quality assurance measures to continuously improve the data quality within the boundary conditions of a high throughput industrial laboratory operating according to the guidelines of ISO 17025 and to meet the requirements of the ITV's on method uncertainties. (author)

  13. The System for Controlling Source and Special Nuclear Material at the Eurochemic Reprocessing Plant

    International Nuclear Information System (INIS)

    Eurochemic is constructing a reprocessing plant near Mol (Belgium). The main characteristics of the plant and the different process steps are summarized. To maintain proper control of source and special nuclear material, the facilities of the company are divided into material balance areas. All transfers into and out of these areas are determined. Depending on their significance for the overall material balance, different precision requirements have been established according to a scale of significance which is briefly discussed. To adjust the book balance, physical inventories are periodically performed. The corresponding inventory procedures are outlined. The books used for nuclear materials accounting and the principles of the accounting system are summarized. (author)

  14. Materials measurement and accounting in an operating plutonium conversion and purification process. Phase I. Process modeling and simulation

    International Nuclear Information System (INIS)

    A model of an operating conversion and purification process for the production of reactor-grade plutonium dioxide was developed as the first component in the design and evaluation of a nuclear materials measurement and accountability system. The model accurately simulates process operation and can be used to identify process problems and to predict the effect of process modifications

  15. Materials measurement and accounting in an operating plutonium conversion and purification process. Phase I. Process modeling and simulation. [PUCSF code

    Energy Technology Data Exchange (ETDEWEB)

    Thomas, C.C. Jr.; Ostenak, C.A.; Gutmacher, R.G.; Dayem, H.A.; Kern, E.A.

    1981-04-01

    A model of an operating conversion and purification process for the production of reactor-grade plutonium dioxide was developed as the first component in the design and evaluation of a nuclear materials measurement and accountability system. The model accurately simulates process operation and can be used to identify process problems and to predict the effect of process modifications.

  16. Some political issues related to future special nuclear materials production

    International Nuclear Information System (INIS)

    The Federal Government must take action to assure the future adequate supply of special nuclear materials for nuclear weapons. Existing statutes permit the construction of advanced defense production reactors and the reprocessing of commercial spent fuel for the production of special materials. Such actions would not only benefit the US nuclear reactor manufacturers, but also the US electric utilities that use nuclear reactors

  17. Structured assessment approach version 1. License submittal document content and format for material control and accounting assessment. Volume II

    Energy Technology Data Exchange (ETDEWEB)

    Parziale, A.A.; Sacks, I.J.

    1979-10-01

    A methodology, the Structured Assessment Approach, has been developed for the assessment of the effectiveness of material control and accounting (MC and A) safeguards systems at nuclear fuel cycle facilities. This methodology has been refined into a computational tool, the SAA Version 1 computational package, that was used first to analyze a hypothetical fuel cycle facility and used more recently to assess operational nuclear plants. The Version 1 analysis package is designed to analyze safeguards systems that prevent the diversion of special nuclear material (SNM) from nuclear fuel cycle facilities and to provide assurance that diversion has not occurred. This report is the second volume, the License Submittal Document Content and Format for Material Control and Accounting Assessment, of a four-volume document. It presents the content and format of the LSD necessary for Material Control and Accounting (MC and A) assessment with the SAA Version 1. The LSD is designed to provide the necessary data input to perform all four stages of analyses associated with the SAA. A full-size but Hypothetical Fuel Cycle Facility (HFCF) is used as an example to illustrate the required input data content and data format and to illustrate the procedure for generating the LSD. Generation of the LSD is the responsibility of the nuclear facility licensee applicant.

  18. Straight-Line -- A nuclear material storage information management system

    Energy Technology Data Exchange (ETDEWEB)

    Nilsen, C. [Sandia National Labs., Livermore, CA (United States); Mangan, D. [Sandia National Labs., Albuquerque, NM (United States)

    1995-12-31

    Sandia National Laboratories is developing Straight-Line -- a pilot system to demonstrate comprehensive monitoring of nuclear material in storage. Straight-Line is an integrated system of sensors providing information that will enhance the safety, security, and international accountability of stored nuclear material. The goals of this effort are to (1) Provide the right sensor information to the right user in a timely manner. (2) Reduce the expenses, risks, and frequency of human inspection of the material. (3) Provide trustworthy data to international inspectors to minimize their need to make on site inspections. In pursuit of these goals, Straight-Line unites technology from Sandia`s Authenticated Item Monitoring System (AIMS) and other programs to communicate the authenticated status of the monitored item back to central magazine receivers. Straight-Line, however, incorporates several important features not found in previous systems: (1) Information Security -- the ability to collect and safely disseminate both classified and unclassified sensor data to users on a need-to-know basis. (2) Integrate into a single system the monitoring needs of safety, security, and international accountability. (3) Incorporate the use of sensors providing analog or digital output. This paper will present the overall architecture and status of the Straight-Line project.

  19. Straight-Line: A nuclear material storage information management system

    Energy Technology Data Exchange (ETDEWEB)

    Nilsen, C.; Mangan, D.

    1995-07-01

    Sandia National Laboratories is developing Straight-Line -- a pilot system to demonstrate comprehensive monitoring of nuclear material in storage. Straight-Line is an integrated system of sensors providing information that will enhance the safety, security, and international accountability of stored nuclear material. The goals of this effort are to: (1) Provide the right sensor information to the right user immediately. (2) Reduce the expenses, risks, and frequency of human inspection of the material. (3) Provide trustworthy data to international inspectors to minimize their need to make on site inspections. In pursuit of these goals, Straight-Line unites technology from Sandia`s Authenticated Item Monitoring System (AIMS) and other programs to communicate the authenticated status of the monitored item back to central magazine receivers. Straight-Line, however, incorporates several important features not found in previous systems: (1) Information Security -- the ability to collect and safely disseminate both classified and unclassified sensor data to users on a need-to-know basis. (2) Integrate into a single system the monitoring needs of safety, security, and international accountability. (3) Incorporate the use of sensors providing analog or digital output. This paper will present the overall architecture and status of the Straight-Line project.

  20. The R and D/operational MC and A [materials control and accounting] interface

    International Nuclear Information System (INIS)

    Improvements in our ability to do materials control and accounting (MC and A) have been steady since the beginning of the nuclear age and the appearance of processes and facilities for handling nuclear materials. The motivation for these improvements has not been just safeguards: the desire for better process control also has played a major role, and the emergence of technology focused on the problems of MC and A has made it possible to pursue such improvements. However, it is a continuing challenge to match the needs of the operational MC and A elements with the capabilities and resources of the R and D community. In the last couple of years this challenge has been addressed very visibly by the DOE's Project Cerberus R and D Committee, which has devised a procedure to encourage closer interactions between the operations and R and D elements. In the particular case of Los Alamos, we have recently concluded the efforts of the Nuclear Materials Management and Safeguards Task Force, which made strong recommendations about the need for close internal cooperation. The issues associated with these activities and the specific means for addressing them, will be of surpassing interest for the future of safeguards

  1. Current trends in nuclear material transportation

    International Nuclear Information System (INIS)

    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)

  2. Protocol to suspend the application of safeguards pursuant to the Agreement of 26 February 1976 between the Agency, the Government of the Federative Republic of Brazil and the Government of the Federal Republic of Germany in the light of the provisions for the application of safeguards pursuant to the Quadripartite Safeguards Agreement between Argentina, Brazil, the Brazilian-Argentine Agency for the Accounting and Control of Nuclear Materials and the IAEA

    International Nuclear Information System (INIS)

    The document reproduces the text of the Protocol of 16 October 1998 suspending the application of safeguards under the Safeguards Agreement (INFCIRC/237) of 26 February 1976 between the Agency, Brazil and the Federal Republic of Germany in the light of the provisions for the application of safeguards pursuant to the Quadripartite Safeguards Agreement between the Agency, Brazil, the Brazilian-Argentine Agency for the Accounting and Control of Nuclear Materials and the IAEA. The Protocol entered into force on 21 October 1999

  3. Accountability and non-proliferation nuclear regime: a review of the mutual surveillance Brazilian-Argentine model for nuclear safeguards; Accountability e regime de nao proliferacao nuclear: uma avaliacao do modelo de vigilancia mutua brasileiro-argentina de salvaguardas nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Xavier, Roberto Salles

    2014-08-01

    The regimes of accountability, the organizations of global governance and institutional arrangements of global governance of nuclear non-proliferation and of Mutual Vigilance Brazilian-Argentine of Nuclear Safeguards are the subject of research. The starting point is the importance of the institutional model of global governance for the effective control of non-proliferation of nuclear weapons. In this context, the research investigates how to structure the current arrangements of the international nuclear non-proliferation and what is the performance of model Mutual Vigilance Brazilian-Argentine of Nuclear Safeguards in relation to accountability regimes of global governance. For that, was searched the current literature of three theoretical dimensions: accountability, global governance and global governance organizations. In relation to the research method was used the case study and the treatment technique of data the analysis of content. The results allowed: to establish an evaluation model based on accountability mechanisms; to assess how behaves the model Mutual Vigilance Brazilian-Argentine Nuclear Safeguards front of the proposed accountability regime; and to measure the degree to which regional arrangements that work with systems of global governance can strengthen these international systems. (author)

  4. 10 CFR 72.78 - Nuclear material transaction reports.

    Science.gov (United States)

    2010-01-01

    ... shall submit a Nuclear Material Transaction Report in computer-readable format as specified in the... shall submit a Nuclear Material Transaction Report in computer-readable format in accordance with... 10 Energy 2 2010-01-01 2010-01-01 false Nuclear material transaction reports. 72.78 Section...

  5. Study of Nuclear Environment and Material Strategy

    International Nuclear Information System (INIS)

    Progress of global warming requires us to establish a low-carbon society. Carbon-dioxide (CO2) is emitted from two major sectors in the world. The largest CO2 emitting sector is power sector having 46 % of the world share. Nuclear power has an important role because it does not emit CO2 while it produces electricity. The second largest sector is transportation and has about 23 % of the world share. 73 % of transportation is land-transportation, that is to say automobile. Therefore, lots of motor-car companies are expressing their vision to supply electric vehicle (EV) or hybrid vehicle (HV) in these few years. In order to manufacture EV and HV, rare-earth materials such as neodymium (Nd) and dysprosium (Dy) are necessary. EV and HV are driven by an electric motor using permanent magnet. Nd is used to improve torque of permanent magnet. Dy is used as supplement for the case of HV in order to enhance thermal resistance because electric motor is exposed to high temperature circumference with combustion engine. 97 % of world supply of rare-earth production is shared by China. The reduction of exportation amount of rare-earth from China to Japan have brought a significant impact on Japan's industries especially for motor-car companies, which are going to supply EV and HV. Japan is going to develop new rare-earth mines outside of China such as in Vietnam. The most important problem relating to rare-earth mining is 'thorium'. The popular minerals containing rare-earth are monazite, bastnasite and so on. Thorium is mostly included in the same minerals. Therefore, thorium is separated whenever rare-earth is refined. Thorium separated in China can be stored for future usage as nuclear fuel. Though thorium began to be considered also in a working group of Atomic Energy Society of Japan since 2010, it is not clear when thorium starts to be used and how much amount of thorium will be consumed. It is estimated that consumption of thorium will be smaller than the production of

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

    International Nuclear Information System (INIS)

    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

  7. Status of U.S. programs for material protection, control ampersand accounting assistance to Ukraine and Kazakstan

    International Nuclear Information System (INIS)

    The United States is one of several donor states providing technical assistance to the Newly Independent States (NIS) of the Former Soviet Union (FSU) for improving their systems for control of nuclear materials. Ukraine and Kazakstan have significant nuclear energy programs. Both countries have committed to nonproliferation of nuclear weapons. They have signed the NPT and have safeguards agreements with the U.S. concerning development of state systems of control, accounting and physical protection of nuclear materials. As directed by the DOE - International Safeguards Division (now the DOE - Russia/NIS Nuclear Materials Security Task Force), technical specialists from several national laboratories, including Argonne, Los Alamos, Oak Ridge, Pacific Northwest and Sandia, as well as representatives of other U.S. Government organizations, such as the NRC, DOD/DNA and the New Brunswick Laboratory, are interacting with government regulatory and facility personnel of Ukraine and Kazakstan. Argonne has program coordination responsibilities for both countries. In support of agreements between the U.S. and Ukraine and the U.S. and Kazakstan, the DOE is responsible for providing technical assistance and training to aid in the evaluation, design, development, and implementation of nuclear material safeguards. This assistance includes: (1) information systems for tracking and reporting the location of nuclear materials, (2) application of nuclear measurement techniques for verifying inventories, (3) material control and accounting (MC ampersand A) systems, and (4) physical protection (PP) systems. Site survey teams, including both MC ampersand A and PP experts from several national labs, have visited Ukraine and Kazakstan. This paper summarizes activities to date and future plans

  8. The Need for Structured Professional Development and Certification amongst Personnel with Accountabilities for Nuclear Security Management and Regulation

    International Nuclear Information System (INIS)

    The International Community has made extensive efforts over recent years to enhance the security of nuclear and other radioactive materials, through a variety of initiatives and programmes at the international, national and organisational level. These have taken the form of support for international instruments including the amendment to the Convention on the Physical Protection of Nuclear Material, the revision of INFCIRC/225, IAEA-led programmes to support Member States, bilateral work to reduce the vulnerability of nuclear and other radioactive materials and, more recently, an emphasis on training and education with the objective of building human capacity and professional competence amongst those personnel with accountabilities for nuclear security. The new focus on human capacity building is both timely and of essential importance; almost all systems, be they for nuclear security or any other field of human endeavour, rely on the effectiveness of both technical and human performance. Deficiencies in either one regularly and predictably result in system failure and the literature is dominated by examples of major incidents that identify failings in professional training, decision making and/or technical equipment failure as the root cause of the incident. This paper reviews the current status of professional development and the availability and potential advantages of certification for those personnel with accountabilities for nuclear security. It addresses the key questions; to what extent should we consider nuclear security management a “recognised” profession that meets the core professional concepts, where can we learn from related fields and share best practices, how do we accelerate the process to engender political and public confidence, and how can the IAEA and Member States take a lead role to achieve a new “norm” for human performance in the field of nuclear security

  9. Accountability and non-proliferation nuclear regime: a review of the mutual surveillance Brazilian-Argentine model for nuclear safeguards

    International Nuclear Information System (INIS)

    The regimes of accountability, the organizations of global governance and institutional arrangements of global governance of nuclear non-proliferation and of Mutual Vigilance Brazilian-Argentine of Nuclear Safeguards are the subject of research. The starting point is the importance of the institutional model of global governance for the effective control of non-proliferation of nuclear weapons. In this context, the research investigates how to structure the current arrangements of the international nuclear non-proliferation and what is the performance of model Mutual Vigilance Brazilian-Argentine of Nuclear Safeguards in relation to accountability regimes of global governance. For that, was searched the current literature of three theoretical dimensions: accountability, global governance and global governance organizations. In relation to the research method was used the case study and the treatment technique of data the analysis of content. The results allowed: to establish an evaluation model based on accountability mechanisms; to assess how behaves the model Mutual Vigilance Brazilian-Argentine Nuclear Safeguards front of the proposed accountability regime; and to measure the degree to which regional arrangements that work with systems of global governance can strengthen these international systems. (author)

  10. Security of Nuclear Material in Transport. Implementing Guide

    International Nuclear Information System (INIS)

    This publication provides guidance to states and their competent authorities on how to implement and maintain a physical protection regime for transport of nuclear material. It will also be useful to shippers or carriers in the design and implementation of their physical protection systems. The publication builds upon the Nuclear Security Recommendations on Physical Protection of Nuclear Material and Nuclear Facilities (INFCIRC/225/Revision 5), IAEA Nuclear Security Series No. 13, and provides additional guidance on how to implement these recommendations in practice

  11. New automated inventory/material accounting system (AIMAS) version for former Soviet Union countries

    Energy Technology Data Exchange (ETDEWEB)

    Kuzminski, Jozef [Los Alamos National Laboratory; Ewing, Tom [ANL; Sakunov, Igor [AVIS CORP., KIEV, UKRAINE; Drapey, Sergey [GEORGE KUZMYCZ TRAINING; Nations, Jim [GREGG PROTECTION SERVICES

    2009-01-01

    AIMAS (Automated Inventory/Material Accounting System) is a PC-based application for site-level nuclear material accountancy that was originally developed in the late 90's as a part of the U.S Department of Energy Assistance Program to Ukraine. Designed to be flexible and secure, plus place minimal demands on computing infrastructure, it was originally developed to run in early Windows operating system (OS) environments like W98 and W3.1. The development, support, and maintenance of AIMAS were transferred to Ukraine in 2002. Because it is highly flexible and can be configured to meet diverse end-user's needs, the software has been used at several facilities in Ukraine. Incorporating added functionality is planned to support nuclear installations in the Republic of Kazakhstan and Uzbekistan, as well. An improved 32-bit version of AIMAS has recently been developed to operate effectively on modern PCs running the latest Windows OS by AVIS, the Ukrainian developer. In the paper we discuss the status of AIMAS, plans for new functions, and describe the strategy for addressing a sustainable software life-cycle while meeting user requirements in multiple FSU countries.

  12. Criteria for Determination of Material Control and Accountability System Effectiveness

    International Nuclear Information System (INIS)

    The Nevada Test Site (NTS) is a test bed for implementation of the Safeguards First Principles Initiative (SFPI), a risk-based approach to Material Control and Accountability (MC and A) requirements. The Comprehensive Assessment of Safeguards Strategies (COMPASS) model is used to determine the effectiveness of MC and A systems under SFPI. Under this model, MC and A is divided into nine primary elements. Each element is divided into sub-elements. Then each sub-element is assigned two values, effectiveness and contribution, that are used to calculate the rating. Effectiveness is a measure of subelement implementation and how well it meets requirements. Contribution is a relative measure of the importance, and functions as a weighting factor. The COMPASS model provides the methodology for calculation of sub-element and element ratings, but not the actual criteria. Each site must develop its own criteria. For the rating to be meaningful, the effectiveness criteria must be objective and based on explicit, measurable criteria. Contribution (weights) must reflect the importance within the MC and A program. This paper details the NTS approach to system effectiveness and contribution values, and will cover the following: the basis for the ratings, an explanation of the contribution 'weights', and the objective, performance based effectiveness criteria. Finally, the evaluation process will be described

  13. Environmental Management Accounting for Cleaner Production: Systematization of Material Flow Cost Accounting (MCFA) into Corporate Management System

    OpenAIRE

    NAKAJIMA, Michiyasu; 中嶌, 道靖

    2011-01-01

    The purpose of this research is to consider the structure of a management system which supports countermeasures for the environment in the manufacturing process by Environmental Management Accounting and particularly by Material Flow Cost Accounting (MFCA) and the features of its management system.

  14. Materials safeguards and accountability in the low enriched uranium conversion-fabrication sector of the fuel cycle

    International Nuclear Information System (INIS)

    Today materials accounting in the low enriched conversion-fabrication sector of the LWR fuel cycle is of increased importance. Low enriched uranium is rapidly becoming a precious metal with current dollar values in the range of one dollar per gram comparing with gold and platinum at 7-8 dollars per gram. In fact, people argue that its dollar value exceeds its safeguards value. Along with this increased financial incentive for better material control, the nuclear industry is faced with the impending implementation of international safeguards and increased public attention over its ability to control nuclear materials. Although no quantity of low enriched uranium (LEU) constitutes a practical nuclear explosive, its control is important to international safeguards because of plutonium production or further enrichment to an explosive grade material. The purpose of the paper is to examine and discuss some factors in the area of materials safeguards and accountability as they apply to the low enriched uranium conversion-fabrication sector. The paper treats four main topics: basis for materials accounting; our assessment of the proposed new IAEA requirements; adequacy of current practices; and timing and direction of future modifications

  15. Scanning of Vehicles for Nuclear Materials

    CERN Document Server

    Katz, J I

    2014-01-01

    Might a nuclear-armed terrorist group or state use ordinary commerce to deliver a nuclear weapon by smuggling it in a cargo container or vehicle? This delivery method would be the only one available to a sub-state actor, and it might enable a state to make an unattributed attack. Detection of a weapon or fissile material smuggled in this manner is difficult because of the large volume and mass available for shielding. Here I review methods for screening cargo containers to detect the possible presence of nuclear threats. Because of the large volume of innocent international commerce, and the cost and disruption of secondary screening by opening and inspection, it is essential that the method be rapid and have a low false-positive rate. Shielding can prevent the detection of neutrons emitted spontaneously or by induced fission. The two promising methods are muon tomography and high energy X-radiography. If they do not detect a shielded threat object they can detect the shield itself.

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

    International Nuclear Information System (INIS)

    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)

  17. Annual report and accounts of the Nuclear Energy Board 1991

    International Nuclear Information System (INIS)

    In a year which saw the passing into law of the Radiological Protection Act 1991, and on the international scene the publication of new Recommendations by the International Commission on Radiological Protection, the Nuclear Energy Board deepened the emphasis of its work on the protection of the public and the environment against the risks associated with ionising radiation. This it did particularly through its programme of monitoring of both artificial and natural radioactivity in the environment, regulation of uses of ionising radiation in medicine and industry, development of emergency response capability and participation in international research activities

  18. Molecular forensic science of nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Wilkerson, Marianne Perry [Los Alamos National Laboratory

    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{sub 2} (An: U, Pu) to form non-stoichiometric species described as AnO{sub 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.

  19. Molecular forensic science of nuclear materials

    International Nuclear Information System (INIS)

    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 AnO2 (An: U, Pu) to form non-stoichiometric species described as AnO2+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.

  20. Decree No. 144/1997 on physical protection of nuclear material and nuclear facilities and on their categorization

    International Nuclear Information System (INIS)

    The Decree, issued by the State Office for Nuclear Safety of the Czech Republic, supersedes previous Czech legislation in the field concerned and is consistent with international documents such as the IAEA document 'The Physical Protection of Nuclear Material' (INFCIRC/225/Rev. 3) and 'The Convention on the Physical Protection of Nuclear Material' (INFCIRC/274/Rev. 1). Comments presented by representatives of the Czech Ministry of the Interior, the Czech Police, the Czech utility CEZ, the two Czech nuclear power plants, and the Nuclear Research Institute were taken into account when setting up the Decree. A facsimile of the Decree is reproduced as published in the official Collection of Acts of the Czech Republic. (P.A.)

  1. ReflectoActive{trademark} Seals for Materials Control and Accountability

    Energy Technology Data Exchange (ETDEWEB)

    Richardson, G.D.; Younkin, J.R.; Bell, Z.W.

    2002-01-01

    The ReflectoActive{trademark} Seals system, a continuously monitored fiber optic, active seal technology, provides real-time tamper indication for large arrays of storage containers. The system includes a PC running the RFAS software, an Immediate Detection Unit (IDU), an Optical Time Domain Reflectometer (OTDR), links of fiber optic cable, and the methods and devices used to attach the fiber optic cable to the containers. When a breach on any of the attached fiber optic cable loops occurs, the IDU immediately signals the connected computer to control the operations of an OTDR to seek the breach location. The ReflectoActive{trademark} Seals System can be adapted for various types of container closure designs and implemented in almost any container configuration. This automatic protection of valued assets can significantly decrease the time and money required for surveillance. The RFAS software is the multi-threaded, client-server application that monitors and controls the components of the system. The software administers the security measures such as a two-person rule as well as continuous event logging. Additionally the software's architecture provides a secure method by which local or remote clients monitor the system and perform administrative tasks. These features provide the user with a robust system to meet today's material control and accountability needs. A brief overview of the hardware, and different hardware configurations will be given. The architecture of the system software, and its benefits will then be discussed. Finally, the features to be implemented in future versions of the system will be presented.

  2. Special Nuclear Material Portal Monitoring at the Nevada Test Site

    International Nuclear Information System (INIS)

    Prior to April 2007, acceptance and performance testing of the various Special Nuclear Material (SNM) monitoring devices at the Nevada Test Site (NTS) was performed by the Radiological Health Instrumentation department. Calibration and performance testing on the PM-700 personnel portal monitor was performed, but there was no test program for the VM-250 vehicle portal monitor. The handheld SNM monitors, the TSA model 470B, were being calibrated annually, but there was no performance test program. In April of 2007, the Material Control and Accountability Manager volunteered to take over performance testing of all SNM portal monitors at NTS in order to strengthen the program and meet U.S. Department of Energy Order requirements. This paper will discuss the following activities associated with developing a performance testing program: changing the culture, learning the systems, developing and implementing procedures, troubleshooting and repair, validating the process, physical control of equipment, acquisition of new systems, and implementing the performance test program

  3. The physical protection of nuclear material and nuclear facilities including activities to combat nuclear terrorism

    International Nuclear Information System (INIS)

    The paper describes present of physical protection of nuclear facilities and materials in the Czech Republic; the basic concept and regulation in physical protection and the effort made to strengthen the national regulatory programmes; the role of the police as a response force and the role of the new private security companies; the upgrading of the physical protection systems at the different types of the nuclear installations to fulfill the more strict requirements of the new Atomic Law No. 18/1997 Coll. and Regulation No. 144/1997 Coll., on physical protection of nuclear materials and nuclear facilities; activities carried out in connection with governmental decision No. 479 dated 19 May 2004 on National action plan to combat terrorism. (author)

  4. Helium behaviour in nuclear waste materials

    Energy Technology Data Exchange (ETDEWEB)

    Wiss, T.; Hiernaut, J.P.; Colle, J.Y.; Maugeri, E.; Raison, P.; Konings, R.; Rondinella, V.V. [European Commission, Joint Research Centre, Institute for Transuranium Elements, P.O. Box 2340, 76125 Karlsruhe (Germany); Roudil, D.; Deschanel, X.; Peuget, S. [Commissariat a l' Energie Atomique, Centre de VALRHO, B.P. 30207 Bagnols-sur-Ceze (France)

    2008-07-01

    Waste conditioning matrices like synthetic zirconolite (CaZrTi{sub 2}O{sub 7}) were fabricated and doped with either the short-lived alpha-emitters {sup 238}Pu or {sup 244}Cm, or with {sup 239}Pu to generate various amounts of helium and of alpha-damage. The samples were annealed in a Knudsen cell, and the helium desorption profiles interpreted in conjunction with parallel radiation damage and previous annealing behaviour studies. To understand the long term behaviour of spent nuclear fuel, UO{sub 2} samples doped with the alpha-emitters {sup 233}U, {sup 238}Pu have been investigated by transmission electron microscopy (TEM), by XRD and by thermal desorption spectroscopy. The release of helium has been explained by the recrystallization of amorphized zirconolite on one hand and partially during alpha-damage recovery in the case of the spent fuel. This study mostly highlights the correlation between restructuring of damaged materials and gas release.

  5. Automation of nuclear material handling operations

    International Nuclear Information System (INIS)

    Automated systems are more and more used in nuclear material handling operations for increasing safety and operation speed and decreasing the personnel exposure to radiations. Some applications of automation to waste or fuel storage overhead cranes are described, showing the evolution of the control philosophy and of the technology used in this field. The computing capabilities and the flexibility of microprocessors make them particularly powerful for applications. The use of multiple microprocessors in a master-slave configuration, mounted on the crane, leads to a rather simple and efficient system. Those systems are described, showing the use of the ''teach-in'' method for data input, bypassing the effects of possibly large tolerances on civil and mechanical works

  6. Travellers’ Accounts as Source-Material for Irish Historians

    OpenAIRE

    Kilgallon, Ann-Marie

    2012-01-01

    Walking, touring and journeying over les chemins d’Irlande, the Saxon and other travellers have offered up gleanings, impressions, sketches or letters about Paddy and his country over several centuries. C. J. Woods’s Travellers’ Accounts is a select repertory of 209 travel accounts of Ireland (accessible in published or manuscript form) spanning the period 1635 to 1950. This innovative guide compels attention to travel writing as a source for Irish history, and thus sets a research agenda. Pr...

  7. 48 CFR 252.242-7004 - Material management and accounting system.

    Science.gov (United States)

    2010-10-01

    ... accounting system. 252.242-7004 Section 252.242-7004 Federal Acquisition Regulations System DEFENSE... CLAUSES Text of Provisions And Clauses 252.242-7004 Material management and accounting system. As prescribed in 242.7204, use the following caluse: Material Management and Accounting System (JUL 2009)...

  8. Material Control and Accounting Design Considerations for High-Temperature Gas Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Trond Bjornard; John Hockert

    2011-08-01

    The subject of this report is domestic safeguards and security by design (2SBD) for high-temperature gas reactors, focusing on material control and accountability (MC&A). The motivation for the report is to provide 2SBD support to the Next Generation Nuclear Plant (NGNP) project, which was launched by Congress in 2005. This introductory section will provide some background on the NGNP project and an overview of the 2SBD concept. The remaining chapters focus specifically on design aspects of the candidate high-temperature gas reactors (HTGRs) relevant to MC&A, Nuclear Regulatory Commission (NRC) requirements, and proposed MC&A approaches for the two major HTGR reactor types: pebble bed and prismatic. Of the prismatic type, two candidates are under consideration: (1) GA's GT-MHR (Gas Turbine-Modular Helium Reactor), and (2) the Modular High-Temperature Reactor (M-HTR), a derivative of Areva's Antares reactor. The future of the pebble-bed modular reactor (PBMR) for NGNP is uncertain, as the PBMR consortium partners (Westinghouse, PBMR [Pty] and The Shaw Group) were unable to agree on the path forward for NGNP during 2010. However, during the technology assessment of the conceptual design phase (Phase 1) of the NGNP project, AREVA provided design information and technology assessment of their pebble bed fueled plant design called the HTR-Module concept. AREVA does not intend to pursue this design for NGNP, preferring instead a modular reactor based on the prismatic Antares concept. Since MC&A relevant design information is available for both pebble concepts, the pebble-bed HTGRs considered in this report are: (1) Westinghouse PBMR; and (2) AREVA HTR-Module. The DOE Office of Nuclear Energy (DOE-NE) sponsors the Fuel Cycle Research and Development program (FCR&D), which contains an element specifically focused on the domestic (or state) aspects of SBD. This Material Protection, Control and Accountancy Technology (MPACT) program supports the present work

  9. Statistical near-real-time accountancy procedures applied to AGNS (Allied General Nuclear Services) minirun data using PROSA

    Energy Technology Data Exchange (ETDEWEB)

    Beedgen, R.

    1988-03-01

    The computer program PROSA (PROgram for Statistical Analysis of near-real-time accountancy data) was developed as a tool to apply statistical test procedures to a sequence of materials balance results for detecting losses of material. First applications of PROSA to model facility data and real plant data showed that PROSA is also usable as a tool for process or measurement control. To deepen the experience for the application of PROSA to real data of bulk-handling facilities, we applied it to uranium data of the Allied General Nuclear Services miniruns, where accountancy data were collected on a near-real-time basis. Minirun 6 especially was considered, and the pulsed columns were chosen as materials balance area. The structure of the measurement models for flow sheet data and actual operation data are compared, and methods are studied to reduce the error for inventory measurements of the columns.

  10. Time factor in physical protection systems defending nuclear facilities and nuclear materials

    International Nuclear Information System (INIS)

    Full text: Various international and national standards and/or recommendations require 'an effective level of physical protection of nuclear materials and nuclear facilities'. This general stipulation will soon be confirmed as obligatory at state level by the revision of the convention of physical protection of nuclear materials now under preparation. The revision would require application of physical protection to domestic nuclear facilities and nuclear materials when in use, in storage and transport, extending legal arrangements (like penalization, extradition, etc.) of the existing convention in this new context. The 'effective level' denotes a wide area of practice and some quantification would be useful in the area which is tantamount to security and depends on technology. In order to discharge the responsibility for implementation of the physical protection measures a license holder will have to assess features of the system and to apply some material grounds for decisions, sometimes leading to expensive consequences. While computer algorithms with probabilistic approach are being used for the purpose, especially for more complicated situation, it seems that use of some single yardstick for the assessment is desirable, especially if it could provide immediate advises for system improvement. Simplicity of approach leads to gains when implementation of analysis results is discussed with financing bodies. One of the features of the physical protection systems that could be used for assessment is certainly timeliness of the operation. The recommendation INFCIRC/225 rev.4 provides some hints like 'promptly', 'timely response' etc. which are inviting to some further work. 'The Handbook of physical protection of nuclear materials and facilities' published recently by the IAEA (IAEA - TECDOC - 1267) summarizes time requirements for the PP system as follows: cumulative time delays caused by obstacles which a perpetrator of an attack has to overcome should be larger

  11. Development of materials for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Haenninen, H. (Aalto Univ. School of Science and Technology, Eng. Materials, Espoo (Finland))

    2010-05-15

    Concerns to material failures of nuclear power plant components have been changing during the years. Corrosion related failures of stainless steel components have been the major concern, especially pipe cracking due to weld sensitization has caused outages and repairs in BWRs. IGSCC of locally cold-worked stainless steel components without sensitization is an emerging problem in aging plants. The major issue concerning failures of stainless steel components has also been environment-assisted cracking (IGSCC and IASCC) of reactor core internal components, where handling of highly active stainless steel materials in repairs is causing also a major concern. In PWRs the long-time concern has been the steam generator tube corrosion damage both on the primary and secondary side as well as the irradiation embrittlement of the reactor pressure vessel steel and its weldments. The new big issue is the Ni-alloy weld metal cracking in reactor pressure vessel safe-end welds and in reactor head and bottom penetrations. Many of these failure modes are time-dependent and, are expected to become more prevalent when the plants are aging. (orig.)

  12. Material Development for Nuclear Fusion and Energy Development Using Actinoids

    OpenAIRE

    Kayano, Hideo

    1994-01-01

    In our Facilities. fundamental researches on nuclear fuels and reactor materials have been performed by making use of JMTR and JOYO. Authors outline original studies among them currently performed by having myself as the core. Research fields in progress are material developments for the nuclear fusion such as ferritic steel and V alloy and energy development using Actinoids. As the material development for practical nuclear fusion, we do those of low activation V alloys, ferritic steels and ...

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

    Science.gov (United States)

    Prasad, Manoj K.; Snyderman, Neal J.; Rowland, Mark S.

    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.

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

    Science.gov (United States)

    Prasad, Mano K.; Snyderman, Neal J.; Rowland, Mark S.

    2015-12-01

    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.

  15. Asymmetrical sabotage tactics, nuclear facilities/materials, and vulnerability analysis

    International Nuclear Information System (INIS)

    Full text: The emerging paradigm of a global community wherein post-modern political violence is a fact of life that must be dealt with by safety and security planners is discussed. This paradigm shift in the philosophy of terrorism is documented by analysis of the emerging pattern of asymmetrical tactics being employed by terrorists. Such philosophical developments in violent political movements suggest a shift in the risks that security and safety personnel must account for in their planning for physical protection of fixed site nuclear source facilities like power generation stations and the eventual storage and transportation of the by-products of these facilities like spent nuclear fuel and other high level wastes. This paper presents a framework for identifying these new political realities and related threat profiles, suggests ways in which security planners and administrators can design physical protection practices to meet these emerging threats, and argues for global adoption of standards for the protection of nuclear facilities that could be used as a source site from which terrorists could inflict a mass contamination event and for standards related to the protection of the waste materials that can be used in the production of radiological weapons of mass victimization. (author)

  16. Nuclear Security Recommendations on Physical Protection of Nuclear Material and Nuclear Facilities (INFCIRC/225/Revision 5). Recommendations (Spanish Edition)

    International Nuclear Information System (INIS)

    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.

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

    International Nuclear Information System (INIS)

    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.

  18. Nuclear Security Recommendations on Physical Protection of Nuclear Material and Nuclear Facilities (INFCIRC/225/Revision 5). Recommendations (Arabic Edition)

    International Nuclear Information System (INIS)

    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.

  19. Nuclear security recommendations on physical protection of nuclear material and nuclear facilities (INFCIRC/225/Revision 5). Recommendations (Chinese Edition)

    International Nuclear Information System (INIS)

    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.

  20. Neutron emission tomography for nuclear fissile materials safeguards

    International Nuclear Information System (INIS)

    Any nondestructive method for fissile assay in spent nuclear fuel must sample a substantial portion of the total number of reactor fuel elements to account for the radial and axial asymmetry of fissile material distribution that may arise during fuel burnup. Cross-sectional scans of the spatial distribution of the fissile isotopes can be tomographically reconstructed while a spent fuel element is being assayed in a lead slowing-down-time (SDT) spectrometer by employing image reconstruction techniques. The SDT approach employs threshold detectors (fission chambers), which measure the induced prompt fast fission neutrons emitted from the fissile isotopes in spent fuel while being interrogated with a slowing pulse of source neutrons. The objectives of this work were to examine to what extent a cross section representing an array of partially void (missing pins) and intact fuel pins could be reconstructed and how sensitive this method is to diversion, spatial burnup distribution, and gross fissile contents consistency

  1. Distributional properties of stochastic shortest paths for smuggled nuclear material

    Energy Technology Data Exchange (ETDEWEB)

    Cuellar, Leticia [Los Alamos National Laboratory; Pan, Feng [Los Alamos National Laboratory; Roach, Fred [Los Alamos National Laboratory; Saeger, Kevin J [Los Alamos National Laboratory

    2011-01-05

    The shortest path problem on a network with fixed weights is a well studied problem with applications to many diverse areas such as transportation and telecommunications. We are particularly interested in the scenario where a nuclear material smuggler tries to succesfully reach herlhis target by identifying the most likely path to the target. The identification of the path relies on reliabilities (weights) associated with each link and node in a multi-modal transportation network. In order to account for the adversary's uncertainty and to perform sensitivity analysis we introduce random reliabilities. We perform some controlled experiments on the grid and present the distributional properties of the resulting stochastic shortest paths.

  2. Microbial Effects on Nuclear Waste Packaging Materials

    International Nuclear Information System (INIS)

    Microorganisms may enhance corrosion of components of planned engineered barriers within the proposed nuclear waste repository at Yucca Mountain (YM). Corrosion could occur either directly, through processes collectively known as Microbiologically Influenced Corrosion (MIC), or indirectly, by adversely affecting the composition of water or brines that come into direct contact with engineered barrier surfaces. Microorganisms of potential concern (bacteria, archea, and fungi) include both those indigenous to Yucca Mountain and those that infiltrate during repository construction and after waste emplacement. Specific aims of the experimental program to evaluate the potential of microorganisms to affect damage to engineered barrier materials include the following: Indirect Effects--(1) Determine the limiting factors to microbial growth and activity presently in the YM environment. (2) Assess these limiting factors to aid in determining the conditions and time during repository evolution when MIC might become operant. (3) Evaluate present bacterial densities, the composition of the YM microbial community, and determining bacterial densities if limiting factors are overcome. During a major portion of the regulatory period, environmental conditions that are presently extant become reestablished. Therefore, these studies ascertain whether biomass is sufficient to cause MIC during this period and provide a baseline for determining the types of bacterial activities that may be expected. (4) Assess biogenic environmental effects, including pH, alterations to nitrate concentration in groundwater, the generation of organic acids, and metal dissolution. These factors have been shown to be those most relevant to corrosion of engineered barriers. Direct Effects--(1) Characterize and quantify microbiological effects on candidate containment materials. These studies were carried out in a number of different approaches, using whole YM microbiological communities, a subset of YM

  3. Microbial Effects on Nuclear Waste Packaging Materials

    Energy Technology Data Exchange (ETDEWEB)

    Horn, J; Martin, S; Carrillo, C; Lian, T

    2005-07-22

    Microorganisms may enhance corrosion of components of planned engineered barriers within the proposed nuclear waste repository at Yucca Mountain (YM). Corrosion could occur either directly, through processes collectively known as Microbiologically Influenced Corrosion (MIC), or indirectly, by adversely affecting the composition of water or brines that come into direct contact with engineered barrier surfaces. Microorganisms of potential concern (bacteria, archea, and fungi) include both those indigenous to Yucca Mountain and those that infiltrate during repository construction and after waste emplacement. Specific aims of the experimental program to evaluate the potential of microorganisms to affect damage to engineered barrier materials include the following: Indirect Effects--(1) Determine the limiting factors to microbial growth and activity presently in the YM environment. (2) Assess these limiting factors to aid in determining the conditions and time during repository evolution when MIC might become operant. (3) Evaluate present bacterial densities, the composition of the YM microbial community, and determining bacterial densities if limiting factors are overcome. During a major portion of the regulatory period, environmental conditions that are presently extant become reestablished. Therefore, these studies ascertain whether biomass is sufficient to cause MIC during this period and provide a baseline for determining the types of bacterial activities that may be expected. (4) Assess biogenic environmental effects, including pH, alterations to nitrate concentration in groundwater, the generation of organic acids, and metal dissolution. These factors have been shown to be those most relevant to corrosion of engineered barriers. Direct Effects--(1) Characterize and quantify microbiological effects on candidate containment materials. These studies were carried out in a number of different approaches, using whole YM microbiological communities, a subset of YM

  4. 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

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    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)

  7. Evaluation of nonaqueous processes for nuclear materials

    International Nuclear Information System (INIS)

    A working group was assigned the task of evaluating the status of nonaqueous processes for nuclear materials and the prospects for successful deployment of these technologies in the future. In the initial evaluation, the study was narrowed to the pyrochemical/pyrometallurgical processes closely related to the processes used for purification of plutonium and its conversion to metal. The status of the chemistry and process hardware were reviewed and the development needs in both chemistry and process equipment technology were evaluated. Finally, the requirements were established for successful deployment of this technology. The status of the technology was evaluated along three lines: (1) first the current applications were examined for completeness, (2) an attempt was made to construct closed-cycle flow sheets for several proposed applications, (3) and finally the status of technical development and future development needs for general applications were reviewed. By using these three evaluations, three different perspectives were constructed that together present a clear picture of how complete the technical development of these processes are

  8. Transport of nuclear material (Part I)

    International Nuclear Information System (INIS)

    TNF - as a 80% subsidiary of NUKEM and 20% of Transnucleaire, Paris - is involved in the transport of radioactive material since 1966 and is a member of the transnuclear group. One main aspect of Transnuklear's activities is the worldwide transport of your fuel in all forms like Uranium Hexafluoride, Uranium metal, fresh and spent fuel elements. In order to accomplish these activities Transnuklear works together with partners in the United States, France, Belgium, Spain, Great Britain and since September 1981 in Canada and Australia. It goes without saying that nobody can handle a nuclear transport job without knowing the international transport regulations such as Imco, ADR, IATA-RAR (Restricted ARticle Regulations) and IAEA Regulations, both the 1973 edition for Europe and Japan and the 1967 edition for the United States. Transport systems for HEU fuel were improved. Concerning transport of fuel with the enrichment less than 20% one can state that the same safety regulations as IAEA, IATA, ADR will apply and that the same containers can be used

  9. Material performance evaluation -Development of the advanced nuclear materials-

    International Nuclear Information System (INIS)

    A multifrequency ACPD system was assembled. A SSRT equipment for stress corrosion cracking test was installed. A 25-ton capacity fatigue test machine was purchased as a first step to assemble a corrosion fatigue test facility. A test loop was designed to simulate the primary water chemistry condition. An Ag/AgCl external reference electrode which can be used at a temperature as high as 280 deg C was fabricated. A high temperature pH electrode was designed for fabrication. A creep test machine was designed conceptually for testing creep behaviors of Zr alloys. Preliminary design requirements were made for the instrumented capsule and a plan was made for using the uninstrumented capsule, as parts of activities to complete an integrated plan of in-reactor materials irradiation test. CHEC computer code which helped improving maintenance program against erosion/corrosion of secondary pipings of nuclear power plants was purchased. Erosion/corrosion of feedwater heater drain line of Kori Unit One was analyzed using the CHEC code as a sample calculation. (Author)

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

    International Nuclear Information System (INIS)

    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.)

  11. US develops neutron to sniff out nuclear material

    CERN Multimedia

    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).

  12. A Review of Neutron Scattering Applications to Nuclear Materials

    OpenAIRE

    Sven C. Vogel

    2013-01-01

    The growing demand for electric energy will require expansion of the amount of nuclear power production in many countries of the world. Research and development in this field will continue to grow to further increase safety and efficiency of nuclear power generation. Neutrons are a unique probe for a wide range of problems related to these efforts, ranging from crystal chemistry of nuclear fuels to engineering diffraction on cladding or structural materials used in nuclear reactors. Increased...

  13. Safety review, assessment and regulatory inspection on nuclear fuel cycle installations and nuclear material control

    International Nuclear Information System (INIS)

    The NNSA conducted surveillance in 1999 on the Yibin Nuclear Fuel Plant (YNFP) and the laboratory for the Qinghua HTR elements. A CP was granted for the Pilot Plant of Spent Fuel Reprocessing in NNFP and a review and assessment on nuclear safety for the construction application of product line with the fuel elements of HWR in the Baotou No. 202 plant and a review and assessment was performed. The NNSA approved the nuclear material license at QNPP and performed surveillance on the nuclear material control for the 6 licensees of nuclear material such as the INET/Tu, QNPJVC etc

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

    International Nuclear Information System (INIS)

    This report covers data for the period from April 1, 1982, through September 30, 1982, and includes accounting corrections for data from earlier periods. These data and explanations, together with the absences of physical indications of any theft attempt, support a finding that during this period no theft or diversion of strategic special nuclear material has occurred

  15. THE DEVELOPMENT OF MATERIAL FLOW INFORMATION BASE OF MANAGEMENT AND ACCOUNTING IN THE CONSTRUCTION INDUSTRY

    OpenAIRE

    Degaltseva Z. V.; Shulepina S. A.; Ovsiyenko E. M.

    2015-01-01

    This article discusses the problems of using indicators of material flow in the financial accounting management accounting system. The authors have created and described the classification of material costs in building units. It allows solving the problems of object of research specifying within a given material flow and inventory control within a given logistics systems. There are different approaches to the valuation of material costs in the article. An important aspect of measures for the ...

  16. Applied Aspects of Material Costs Accounting and Their Impact on Volatile Oil Produce Cost

    OpenAIRE

    Olena Sorokina

    2014-01-01

    Rational use of material resources is one of the main ways to reduce production cost since the share of material costs in various industries production cost ranges from 50 to 90 %.The article covers the research into the applied aspects of accounting material costs for volatile oil products manufacture. The purpose of the study is the development of recommendations for improvement of material cost accounting and calculation of volatile oil products cost. The author has offered a list of volat...

  17. 1984 EC enquiry into the needs for nuclear reference materials (Z>89)

    International Nuclear Information System (INIS)

    For years now, experts in the nuclear field have expressed and pointed out the widespread need for Nuclear Reference Materials (NRMs) in the whole of the nuclear fuel cycle. NRMs were defined as actinides with well-characterized chemical, isotopic and/or physical properties for use as a common base for the calibration of instruments and checking of analytical methods. Since nuclear energy from fission reactors is an increasing contributor to the electricity generating capacity in the EC, there is an equivalent demand for accurate analytical measurements in the various stages of the fuel cycle and in associated fields such as: commercial transactions, production control, nuclear material accounting (safeguards), waste disposal, environmental and health physics, research and development. An essential element for improving analyses and measurements is the availability and use of the appropriate NRMs

  18. Material Protection, Accounting, and Control Technologies (MPACT): Modeling and Simulation Roadmap

    Energy Technology Data Exchange (ETDEWEB)

    Cipiti, Benjamin [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Dunn, Timothy [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Durbin, Samual [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Durkee, Joe W. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); England, Jeff [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Jones, Robert [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Ketusky, Edward [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Li, Shelly [Idaho National Lab. (INL), Idaho Falls, ID (United States); Lindgren, Eric [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Meier, David [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Miller, Michael [Idaho National Lab. (INL), Idaho Falls, ID (United States); Osburn, Laura Ann [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Pereira, Candido [Argonne National Lab. (ANL), Argonne, IL (United States); Rauch, Eric Benton [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Scaglione, John [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Scherer, Carolynn P. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Sprinkle, James K. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Yoo, Tae-Sic [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-08-05

    The development of sustainable advanced nuclear fuel cycles is a long-term goal of the Office of Nuclear Energy’s (DOE-NE) Fuel Cycle Technologies program. The Material Protection, Accounting, and Control Technologies (MPACT) campaign is supporting research and development (R&D) of advanced instrumentation, analysis tools, and integration methodologies to meet this goal (Miller, 2015). This advanced R&D is intended to facilitate safeguards and security by design of fuel cycle facilities. The lab-scale demonstration of a virtual facility, distributed test bed, that connects the individual tools being developed at National Laboratories and university research establishments, is a key program milestone for 2020. These tools will consist of instrumentation and devices as well as computer software for modeling. To aid in framing its long-term goal, during FY16, a modeling and simulation roadmap is being developed for three major areas of investigation: (1) radiation transport and sensors, (2) process and chemical models, and (3) shock physics and assessments. For each area, current modeling approaches are described and gaps and needs are identified.

  19. Material Protection, Accounting, and Control Technologies (MPACT): Modeling and Simulation Roadmap

    Energy Technology Data Exchange (ETDEWEB)

    Cipiti, Benjamin [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Dunn, Timothy [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Durbin, Samual [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Durkee, Joe W. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); England, Jeff [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Jones, Robert [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Ketusky, Edward [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Li, Shelly [Idaho National Lab. (INL), Idaho Falls, ID (United States); Lindgren, Eric [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Meier, David [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Miller, Michael [Idaho National Lab. (INL), Idaho Falls, ID (United States); Osburn, Laura Ann [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Pereira, Candido [Argonne National Lab. (ANL), Argonne, IL (United States); Rauch, Eric Benton [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Scaglione, John [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Scherer, Carolynn P. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Sprinkle, James K. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Yoo, Tae-Sic [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-08-05

    The development of sustainable advanced nuclear fuel cycles is a long-term goal of the Office of Nuclear Energy’s (DOE-NE) Fuel Cycle Technologies program. The Material Protection, Accounting, and Control Technologies (MPACT) campaign is supporting research and development (R&D) of advanced instrumentation, analysis tools, and integration methodologies to meet this goal. This advanced R&D is intended to facilitate safeguards and security by design of fuel cycle facilities. The lab-scale demonstration of a virtual facility, distributed test bed, that connects the individual tools being developed at National Laboratories and university research establishments, is a key program milestone for 2020. These tools will consist of instrumentation and devices as well as computer software for modeling. To aid in framing its long-term goal, during FY16, a modeling and simulation roadmap is being developed for three major areas of investigation: (1) radiation transport and sensors, (2) process and chemical models, and (3) shock physics and assessments. For each area, current modeling approaches are described, and gaps and needs are identified.

  20. Cooperative efforts of the materials protection control and accounting program at the electrochemical plant (Krasnoyarsk-45) in Russia-011

    Energy Technology Data Exchange (ETDEWEB)

    Moore, L.

    1998-07-22

    The USDOE Material Protection Control and Accountability Program (MPC&A) has established a Project Team with the goal of providing the Russian Electrochemical Plant (ECP) with equipment and training to enable ECP to evaluate, develop, and implement a comprehensive plan and systems for physical protection, material controls, and accountancy upgrades. The MPC&A project will provide for improvements such as risk assessments, access control upgrades, computerized MC&A, communications systems upgrades, building perimeter surveillance and intrusion detection upgrades, vault upgrades, metal and nuclear material detection upgrades, along with mass measurement and non- destructive analysis (NDA) instrumentation. This paper outlines the overall objectives of the MPC&A project at the Electrochemical Plant.

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

    International Nuclear Information System (INIS)

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

  2. Nuclear Security Recommendations on Radioactive Material and Associated Facilities: Recommendations

    International Nuclear Information System (INIS)

    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.

  3. Materialism Moderates the Effect of Accounting for Time on Prosocial Behaviors.

    Science.gov (United States)

    Li, Jibo; Chen, Yingying; Huang, Xiting

    2015-01-01

    Accounting for time is defined as putting a price on time. Researchers have demonstrated that accounting for time reduces the time individuals spend on others; however, its association with monetary donations has not been examined. We hypothesized that accounting for time will activate a utility mindset that would affect one's allocation of time and money. In Study 1, the mediating effect of utility mindsets on the relationship between accounting for time and prosocial behavior was examined. In Study 2, we examined the effect of accounting for time on time spent helping and donating money, and the moderating role of material values on the relationship between accounting for time and prosocial behavior. Results showed that accounting for time activated a mindset of utility maximization that, in turn, reduced participants' prosocial behavior; moreover, materialism moderated the effect of accounting for time on prosocial behavior. PMID:25751602

  4. Method of producing fugitive binder-containing nuclear fuel material

    International Nuclear Information System (INIS)

    A nuclear fuel material green body of density from about 30 to 70% of theoretical density having tensile strength and plasticity adequate to maintain the integrity of the body during processing leading to ultimate sintered condition is produced by adding an amine carbonate or carbamate or mixture thereof to a particulate mass of the nuclear fuel material under conditions resulting in reaction with the amine compound to form a water-soluble compound effective as a binder for the particulate material

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

    International Nuclear Information System (INIS)

    The objective if to determine whether the Department of Energy (Department) was adequately managing its nuclear materials provided to domestic licensees. The audit was performed from February 2007 to September 2008 at Department Headquarters in Washington, DC, and Germantown, MD; the Oak Ridge Office and the Oak Ridge National Laboratory in Oak Ridge, TN. In addition, we visited or obtained data from 40 different non-Departmental facilities in various states. To accomplish the audit objective, we: (1) Reviewed Departmental and Nuclear Regulatory Commission (NRC) requirements for the control and accountability of nuclear materials; (2) Analyzed a Nuclear Materials Management and Safeguards System (NMMSS) report with ending inventory balances for Department-owned nuclear materials dated September 30, 2007, to determine the amount and types of nuclear materials located at non-Department domestic facilities; (3) Held discussions with Department and NRC personnel that used NMMSS information to determine their roles and responsibilities related to the control and accountability over nuclear materials; (4) Selected a judgmental sample of 40 non-Department domestic facilities; (5) Met with licensee officials and sent confirmations to determine whether their actual inventories of Department-owned nuclear materials were consistent with inventories reported in the NMMSS; and, (6) Analyzed historical information related to the 2004 NMMSS inventory rebaselining initiative to determine the quantity of Department-owned nuclear materials that were written off from the domestic licensees inventory balances. This performance audit was conducted in accordance with generally accepted Government auditing standards. Those standards require that we plan and perform the audit to obtain sufficient, appropriate evidence to provide a reasonable basis for our findings and conclusions based on our audit objective. We believe that the evidence obtained provides a reasonable basis for our

  6. Nuclear Energy Enabling Technologies (NEET) Reactor Materials: News for the Reactor Materials Crosscut, May 2016

    Energy Technology Data Exchange (ETDEWEB)

    Maloy, Stuart Andrew [Los Alamos National Lab. (LANL), Los Alamos, NM (United States). Materials Science in Radiation and Dynamics Extremes

    2016-09-26

    In this newsletter for Nuclear Energy Enabling Technologies (NEET) Reactor Materials, pages 1-3 cover highlights from the DOE-NE (Nuclear Energy) programs, pages 4-6 cover determining the stress-strain response of ion-irradiated metallic materials via spherical nanoindentation, and pages 7-8 cover theoretical approaches to understanding long-term materials behavior in light water reactors.

  7. Nuclear energy and materials in the 21st century

    International Nuclear Information System (INIS)

    The Global Nuclear Vision Project at the Los Alamos National Laboratory is examining a range of long-term nuclear energy futures as well as exploring and assessing optimal nuclear fuel-cycle and material strategies. An established global energy, economics, environmental (E3) model has been adopted and modified with a simplified, but comprehensive and multi-regional, nuclear energy module. Consistent nuclear energy scenarios are constructed, where future demands for nuclear power are projected in price competition with other energy sources under a wide range of long-term (∼2100) demographic, economic, policy, and technological drivers. A spectrum of futures is examined at two levels in a hierarchy of scenario attributes in which drivers are either external or internal to nuclear energy. The result reported examine departures from a basis scenario and are presented in the following order of increasing specificity: (a) definition and parametric variations of the basis scenario; (b) comparison of the basis scenario with other recent studies; (c) parametric studies that vary upper-level hierarchical scenario attributes (external drivers); and (d) variations of the lower-level scenario attributes (internal drivers). Impacts of a range of nuclear fuel-cycle scenarios are reflected back to the higher-level scenario attributes that characterize particular nuclear energy scenarios. Special attention is given to the role of nuclear materials inventories (in magnitude, location, and form) and their contribution to the long-term sustainability of nuclear energy, the future competitiveness of both conventional and advanced nuclear reactors, and proliferation risk

  8. French National Safeguards and EDF: 20 Years of Cooperation for the Benefit of Nuclear Material Control

    International Nuclear Information System (INIS)

    Since 1980, considering its nuclear situation and conscious of its national and international responsibilities in terms of national public security and nuclear non proliferation, the French government set up a national safeguards system under the authority of the Ministry in charge of Industry, a mission of which is to ensure protection and control of nuclear materials. France has developed a comprehensive fuel cycle from mine to reprocessing plants, in which the 59 nuclear power plants operated by Electricite de France (EDF) represent a nodal point. This paper presents the feedback resulting from more than 20 years of implementation of the regulation by the operator and control by the inspectorate. The first part of this paper recalls the French legal framework regarding the use of nuclear materials in nuclear power plants. Emphasis is put on French specificities in terms of nuclear material accountancy and control (NMCandA) and also on the situation of nuclear power plants within this control The second part shows how EDF is organized in order to fulfill its obligations in terms of nuclear material management. A description of the different responsibilities held within the company is given and illustrated by practical examples. The last part of this paper deals with the feedback arising from more than 20 years in the control of nuclear materials held in power plants. Operator's point of view as well as inspectors' one are presented. This point will be highlighted by presenting various actions led jointly by EDF and the competent Authority in order to make the NMCandA more efficient. Finally, demonstration is made that this cooperation not only improves the control in the French nuclear power plants in terms of NMCandA but also provides an enriching experience, which enhances the operator's and the inspector's skills

  9. Nuclear Weapons Effects (Self-Teaching Materials).

    Science.gov (United States)

    Defense Civil Preparedness Agency (DOD), Battle Creek, MI.

    Developed by the Civil Defense Preparedness Agency, this autoinstructional text deals with nuclear weapons effects. The destructive effects of an atomic blast are first introduced, and then long-term radioactive consequences are stressed. (CP)

  10. Advanced material accountancy glove box assay system for process material at PFPF.

    Energy Technology Data Exchange (ETDEWEB)

    Maruyama, H. (Hajime); Fujiwara, S. (Shigeo); Takahashi, S. (Saburo); Kuno, K.; Menlove, Howard O.; Wenz, T. R. (Tracy R.)

    2002-01-01

    The Material Accountancv Glove Box Assay System (MAGB) is a neutron coincidence counting system that has been developed under the akeement between Japan Nuclear Cycle Development Institute (JNC) and Los Alamos National Laboratory (LANL) in order to measure plutonium in the MOX transfer container in the glove box at Plutonium Fuel Production Facility (PFPF) in Japan. The system was installed at PFPF in August 1989 and afterwards it has been using for verification ofplutonium in the transfer container by inspectorate during inspection Process equipment to improve its performance has been installed in the PFPF fabrication line. As a result the number of sample requiredfor inspection increased. Since MAGBs were only used, it was anticipated that the reduction of the time of sampling and movement time of nuclear materialfor verification would be difficult. Furthermore, the sample has to be taken from the transfer containers that contain a large amount of plutonium. Therefore, in order to reduce the time for sampling, time required for the transfer container to arrive at sampling point, and personal radiation exposure, the integrated MAGB system combined with High resolution gamma-ray spectroscopy (HRGS), called M G B, was developed. This system was installed at PFPF in August 2000, and then, the functional test and the calibration were carried out in the presence of inspectorate. In the course of these activities, the data that is necessary for evaluating the system were fully acquired The system is now being in the process of evaluation whether it can be used as an attended safeguards system for International Atomic Energy Agency (IAEA) and Japan Safeguards Office (JSGO).

  11. 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.

  12. 10 CFR 75.22 - Accounting records.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Accounting records. 75.22 Section 75.22 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) SAFEGUARDS ON NUCLEAR MATERIAL-IMPLEMENTATION OF US/IAEA AGREEMENT Material Accounting and Control for Facilities § 75.22 Accounting records. (a) The accounting records required by §...

  13. Structural properties of the material control and accounting system

    Energy Technology Data Exchange (ETDEWEB)

    1978-12-01

    A unified digraph approach is proposed for the assessment of the structure of the MC and A System. The approach emphasizes the two structural aspects of the system: vulnerability and reliability. Vulnerability is defined as a possibility of loosing connectedness in a given structure due to line and/or node removals. It is purely deterministic notion which leads to a qualitative analysis of redundancy of connections in the corresponding system. Reliability of the MC and A System structure provides a more quantitative way of assessing how safe the system is to random failures of the links representing lines of communication, material paths, monitors, and the components of the power supply network. By assigning probabilities to the lines and nodes of the corresponding digraph, the least reliable path can be used as a measure of the goodness of the system, which can be computed by efficient shortest path algorithms. Both vulnerability and reliability considerations are important in determining the effect of tampering of an adversary with the elements of the MC and M System.

  14. Structural properties of the material control and accounting system

    International Nuclear Information System (INIS)

    A unified digraph approach is proposed for the assessment of the structure of the MC and A System. The approach emphasizes the two structural aspects of the system: vulnerability and reliability. Vulnerability is defined as a possibility of loosing connectedness in a given structure due to line and/or node removals. It is purely deterministic notion which leads to a qualitative analysis of redundancy of connections in the corresponding system. Reliability of the MC and A System structure provides a more quantitative way of assessing how safe the system is to random failures of the links representing lines of communication, material paths, monitors, and the components of the power supply network. By assigning probabilities to the lines and nodes of the corresponding digraph, the least reliable path can be used as a measure of the goodness of the system, which can be computed by efficient shortest path algorithms. Both vulnerability and reliability considerations are important in determining the effect of tampering of an adversary with the elements of the MC and M System

  15. Special Nuclear Material Portal Monitoring at the Nevada Test Site

    International Nuclear Information System (INIS)

    In the past, acceptance and performance testing of the various Special Nuclear Material (SNM) monitoring devices at the Nevada Test Site has been performed by the Radiological Health Instrumentation Department. Calibration and performance tests on the PM-700 personnel portal monitor were performed but there was no test program for the VM-250 vehicle portal monitor because it had never been put into service. The handheld SNM monitors, the TSA model 470B, were being calibrated annually, but there was no program in place to test them quarterly. In April of 2007, the Material Control and Accountability (MC and A) Manager at the time decided that the program needed to be strengthened and MC and A took over performance testing of all SNM portal monitoring equipment. This paper will discuss the following activities associated with creating a performance testing program: changing the culture, learning the systems, writing procedures, troubleshooting/repairing, validating the process, control of equipment, acquisition of new systems, and running the program

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

    International Nuclear Information System (INIS)

    This report provides and explains the differences between the amounts of nuclear materials charged to DOE facilities and the amounts that could be physically inventoried. This report covers data for the period from October 1, 1979, through March 31, 1980, and includes accounting corrections for data from earlier periods. It is the seventh such semiannual report. These data and explanations, together with the absences of physical indications of any theft attempt, support a finding that during this period no theft or diversion of strategic spcial nuclear material has occurred

  17. 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.

  18. Source Book of Educational Materials for Nuclear Medicine.

    Science.gov (United States)

    Pijar, Mary Lou, Comp.; Lewis, Jeannine T., Comp.

    The contents of this sourcebook of educational materials are divided into the following sections: Anatomy and Physiology; Medical Terminology; Medical Ethics and Department Management; Patient Care and Medical Decision-Making; Basic Nuclear Medicine; Diagnostic in Vivo; Diagnostic in Vitro; Pediatric Nuclear Medicine; Radiation Detection and…

  19. In-field analysis and assessment of nuclear material

    International Nuclear Information System (INIS)

    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

  20. Information management in the design of materials control and accountability systems

    International Nuclear Information System (INIS)

    In the initial stage of a materials accounting system design, fundamental decisions are made about the data to be acquired, the means for acquisition, and the location and timing of the acquisition. The data to be acquired are determined by their intended use in the analysis, reporting, and decision processes. This paper presents information management methods for materials accounting systems based on experience in system development at DOE facilities. Specifically, the authors describe principles for the acquisition and organization of data for a materials control and accountability (MC and A) system

  1. An introduction to nuclear materials fundamentals and applications

    CERN Document Server

    Linga Murty, K

    2013-01-01

    Covering both fundamental and advanced aspects in an accessible way, this textbook begins with an overview of nuclear reactor systems, helping readers to familiarize themselves with the varied designs. Then the readers are introduced to different possibilities for materials applications in the various sections of nuclear energy systems. Materials selection and life prediction methodologies for nuclear reactors are also presented in relation to creep, corrosion and other degradation mechanisms. An appendix compiles useful property data relevant for nuclear reactor applications. Throughout the book, there is a thorough coverage of various materials science principles, such as physical and mechanical metallurgy, defects and diffusion and radiation effects on materials, with serious efforts made to establish structure-property correlations wherever possible. With its emphasis on the latest developments and outstanding problems in the field, this is both a valuable introduction and a ready reference for beginners...

  2. Real-Time Characterization of Special Nuclear Materials

    Energy Technology Data Exchange (ETDEWEB)

    Walston, Sean [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Candy, Jim [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Chambers, Dave [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Chandrasekaran, Hema [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Snyderman, Neal [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2015-09-04

    When confronting an item that may contain nuclear material, it is urgently necessary to determine its characteristics. Our goal is to provide accurate information with high-con dence as rapidly as possible.

  3. Beryllium - A Unique Material in Nuclear Applications

    International Nuclear Information System (INIS)

    Beryllium, due to its unique combination of structural, chemical, atomic number, and neutron absorption cross section characteristics, has been used successfully as a neutron reflector for three generations of nuclear test reactors at the Idaho National Engineering and Environmental Laboratory (INEEL). The Advanced Test Reactor (ATR), the largest test reactor in the world, has utilized five successive beryllium neutron reflectors and is scheduled for continued operation with a sixth beryllium reflector. A high radiation environment in a test reactor produces radiation damage and other changes in beryllium. These changes necessitate safety analysis of the beryllium, methods to predict performance, and appropriate surveillances. Other nuclear applications also utilize beryllium. Beryllium, given its unique atomic, physical, and chemical characteristics, is widely used as a ''window'' for x-rays and gamma rays. Beryllium, intimately mixed with high-energy alpha radiation emitters has been successfully used to produce neutron sources. This paper addresses operational experience and methodologies associated with the use of beryllium in nuclear test reactors and in ''windows'' for x-rays and gamma rays. Other nuclear applications utilizing beryllium are also discussed

  4. Special nuclear material inventory sampling plans

    International Nuclear Information System (INIS)

    This paper presents improved procedures for obtaining statistically valid sampling plans for nuclear facilities. The double sampling concept and methods for developing optimal double sampling plans are described. An algorithm is described that is satisfactory for finding optimal double sampling plans and choosing appropriate detection and false alarm probabilities

  5. Erosion and corrosion of nuclear power plant materials

    International Nuclear Information System (INIS)

    This conference is composed of 23 papers, grouped in 3 sessions which main themes are: analysis of corrosion and erosion damages of nuclear power plant equipment and influence of water chemistry, temperature, irradiations, metallurgical and electrochemical factors, flow assisted cracking, stress cracking; monitoring and control of erosion and corrosion in nuclear power plants; susceptibility of structural materials to erosion and corrosion and ways to improve the resistance of materials, steels, coatings, etc. to erosion, corrosion and cracking

  6. Evaluation and development of advanced nuclear materials: IAEA activities

    International Nuclear Information System (INIS)

    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

  7. Structural integrity of materials in nuclear service: a bibliography

    International Nuclear Information System (INIS)

    This report contains 679 abstracts from the Nuclear Safety Information Center (NSIC) computer file dated 1973 through 1976 covering material properties with respect to structural integrity. All materials important to the nuclear industry (except concrete) are covered for mechanical properties, chemical properties, corrosion, fracture or failure, radiation damage, creep, cracking, and swelling. Keyword, author, and permuted-title indexes are included for the convenience of the user

  8. Determination of residual gases in nuclear materials by vacuum fusion

    International Nuclear Information System (INIS)

    The presence of residual gases (hydrogen, nitrogen and oxygen) in nuclear materials considerably affects their mechanical and thermal properties. This problem has stimulated the development of precise and efficient methods of analysis, applicable to the determination and quality control of impurities in these materials. The most suitable technique for this purpose is high vacuum fusion. The feasibility of the method was checked with steel, Zircaloy and nuclear fuel samples. The results experimentally determined are in good agreement with the specified values. (Author)

  9. Structural integrity of materials in nuclear service: a bibliography

    Energy Technology Data Exchange (ETDEWEB)

    Heddleson, F.A.

    1977-06-07

    This report contains 679 abstracts from the Nuclear Safety Information Center (NSIC) computer file dated 1973 through 1976 covering material properties with respect to structural integrity. All materials important to the nuclear industry (except concrete) are covered for mechanical properties, chemical properties, corrosion, fracture or failure, radiation damage, creep, cracking, and swelling. Keyword, author, and permuted-title indexes are included for the convenience of the user.

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    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.

  12. Nuclear Security Recommendations on Nuclear and Other Radioactive Material out of Regulatory Control: Recommendations (Arabic Edition)

    International Nuclear Information System (INIS)

    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.

  13. Nuclear Security Recommendations on Nuclear and Other Radioactive Material out of Regulatory Control: Recommendations (Russian Edition)

    International Nuclear Information System (INIS)

    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.

  14. Nuclear Security Recommendations on Nuclear and other Radioactive Material out of Regulatory Control: Recommendations (Spanish Edition)

    International Nuclear Information System (INIS)

    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.

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

    International Nuclear Information System (INIS)

    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

  16. Advanced materials for space nuclear power systems

    Science.gov (United States)

    Titran, Robert H.; Grobstein, Toni L.; Ellis, David L.

    1991-01-01

    The overall philosophy of the research was to develop and characterize new high temperature power conversion and radiator materials and to provide spacecraft designers with material selection options and design information. Research on three candidate materials (carbide strengthened niobium alloy PWC-11 for fuel cladding, graphite fiber reinforced copper matrix composites for heat rejection fins, and tungsten fiber reinforced niobium matrix composites for fuel containment and structural supports) considered for space power system applications is discussed. Each of these types of materials offers unique advantages for space power applications.

  17. Toward an Evolutive and Tightly Integrated Information System for Nuclear Materials Management

    Energy Technology Data Exchange (ETDEWEB)

    Dessoude, O. [Euriware (Areva Group), 25 avenue de Tourville, Equeurdreville, 50100 (France)

    2009-06-15

    From a nuclear materials management standpoint, spent-fuel recycling is considered a very challenging activity. This challenge has its positive counterpart as a lot has been learned from confronting a large variety of nuclear materials, complex material transfers and transformations. Since the inception of its computerized nuclear materials management system, AREVA NC La Hague has relied upon its IT subsidiary EURIWARE for software design and development. In 2003, the founding milestone was the implementation of the new GMP software package (Gestion des Matieres et des Produits - Materials and Products Management). GMP was underpinned by the following principles: reliability, transparency and close integration with the process control layer, so as to mitigate human errors and keep the management process smooth and efficient. In 2005, another major milestone was reached with CMNR (Comptabilite des Matieres Nucleaires Reglementaire - Regulatory Nuclear Materials Accountancy), a system in charge of local accounting and multi-site consolidation at corporate level. In spite of an auspicious start, GMP came up against the same stumbling block as many information systems: the multiplication of interfaces and technologies (entropy increasing over time). For the sake of maintenance, evolutions and performance, AREVA has decided a progressive modernization of its Nuclear Materials Management (NMM) information system. The underlying principle is a clear separation between the main functions: - Physical Follow-up, performed at the plant-level, - Regulatory Accountancy (for IRSN, EURATOM and IAEA safeguards), offering consolidation at the corporate level, - Patrimonial Accountancy (allocation of materials and conditioned wastes to AREVA's customers). The pivotal piece of this multi-year programme is the implementation of a dedicated data repository. We describe its main building blocks and demonstrate how it helps in managing changes to regulation, products, customers and

  18. 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...

  19. Nuclear forensics of special nuclear material at Los Alamos: three recent studies

    Energy Technology Data Exchange (ETDEWEB)

    Tandon, Lav [Los Alamos National Laboratory; Gallimore, David L [Los Alamos National Laboratory; Garduon, Katherine [Los Alamos National Laboratory; Keller, Russell C [Los Alamos National Laboratory; Kuhn, Kevin J [Los Alamos National Laboratory; Lujan, Elmer J [Los Alamos National Laboratory; Martinez, Alexander [Los Alamos National Laboratory; Myers, Steven C [Los Alamos National Laboratory; Moore, Steve S [Los Alamos National Laboratory; Porterfield, Donivan R [Los Alamos National Laboratory; Schwartz, Daniel S [Los Alamos National Laboratory; Spencer, Khalil J [Los Alamos National Laboratory; Townsend, Lisa E [Los Alamos National Laboratory; Xu, Ning [Los Alamos National Laboratory

    2010-01-01

    Nuclear forensics of special nuclear materials is a highly specialized field because there are few analytical laboratories in the world that can safely handle nuclear materials, perform high accuracy and precision analysis using validated analytical methods. The goal of nuclear forensics is to establish an unambiguous link between illicitly trafficked nuclear material and its origin. The Los Alamos National Laboratory Nuclear Materials Signatures Program has implemented a graded 'conduct of operations' type approach for determining the unique nuclear, chemical, and physical signatures needed to identify the manufacturing process, intended use, and origin of interdicted nuclear material. In our approach an analysis flow path was developed for determining key signatures necessary for attributing unknown materials to a source. This analysis flow path included both destructive (i.e., alpha spectrometry, ICP-MS, ICP-AES, TIMS, particle size distribution, density and particle fractionation) and non-destructive (i.e., gamma-ray spectrometry, optical microscopy, SEM, XRD, and x-ray fluorescence) characterization techniques. Analytical techniques and results from three recent cases characterized by this analysis flow path along with an evaluation of the usefulness of this approach will be discussed in this paper.

  20. Technology development for nuclear material safeguards -A study on the direct use of spent PWR fuel in CANDU-

    International Nuclear Information System (INIS)

    The research contents of the passed one year were the conceptual design of nuclear material measurement points, of near real time accounting system and of unattended monitoring system for detection of nuclear material diversion. The passive neutron detection system was decided as a proper way of detection of plutonium in the spent fuels and the neutrons emitted by each isotopes were investigated. Also, material balance area and major measurement points were selected and related computer code was used for the near real time accounting in DUPIC facility. (Author)

  1. Nuclear data for radiation damage estimates for reactor structural materials

    International Nuclear Information System (INIS)

    The IAEA Consultants' Meeting on Nuclear Data for Radiation Damage Estimates for Reactor Structural Materials was convened by the IAEA Nuclear Data Section in Santa Fe, New Mexico, USA from 20-22 May 1985. The meeting was attended by 17 participants from 10 countries and 2 international organizations. The main objectives of the meeting were to review the status of displacement cross sections and the requirements for nuclear data needed for radiation damage estimates in reactor structural materials, and to develop recommendations for future activities in this field. This publication contains the text of all the papers prepared especially for this meeting including the conclusions and recommendations worked out during the meeting

  2. Development of a Pedestrian Special Nuclear Material Radiation Monitor

    Institute of Scientific and Technical Information of China (English)

    2001-01-01

    Special nuclear material (SNM) monitor equipped at the exits of a protected SNM area can offer a rapid, effective means to search and prevent from unauthorized movement of SNM. In order to apply the detecting technique for SNM to nuclear field and improve the ability to nuclear material control, a pedestrian SNM monitor and a vehicle SNM monitor both with plastic scintillate detector will be developed during the years from 2001 to 2005. The overall design of the pedestrian SNM monitors, the design of relative electronics and control unit and relative mechanical design and machining has been performed in the year 2001. This equipment will be established by the end

  3. A Uniform Framework of Global Nuclear Materials Management

    International Nuclear Information System (INIS)

    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

  4. 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.

  5. Enhancing the Material Control & Accounting Measurement System at the State Scientific Center of the Russian Federation - Institute for Physics and Power Engineering named after A.I. Leypunsky

    Energy Technology Data Exchange (ETDEWEB)

    Scherer, Carolynn P. [Los Alamos National Laboratory; Bezhunov, Gennady M. [IPPE; Bogdanov, Sergey A. [IPPE; Gorbachev, Vyacheslav M. [IPPE; Ryazanov, Boris G. [IPPE; Talanov, Vladimir V. [IPPE

    2012-07-11

    Nuclear material control and accounting (NMCA) system is improving under cooperation with USA national laboratories. Standard reference materials (RMs) and measurement techniques certified at IPPE level are required for: instrument calibration, verification measurements of parameters of items and materials, measurement error estimation, and quality control measurements. We present the main results for development of nuclear RMs for two uranium strata and the results for certification of three measurement techniques (MT) for U-235 mass fraction in uranium and U-235 mass in items. We present the results for developing measurement techniques for Pu-239 in PuO{sub 2}.

  6. How does an old firm learn new tricks? : A material account of entrepreneurial opportunity

    OpenAIRE

    Roscoe, Philip John; Discua-Cruz, Allan; Howorth, Carole

    2012-01-01

    Opportunity has become the central concept in entrepreneurship. Discovery focused accounts assume opportunity to be objective and to exist independently of the entrepreneur. Process-focused studies critique such notions. We contribute to process-based conceptions of entrepreneurship with an account of opportunity as historically specific and materially embedded. Drawing on Latour we argue that opportunities are constituted through dense material networks. We argue that opportunity and entrepr...

  7. Authentication and Interpretation of Weight Data Collected from Accountability Scales at Global Nuclear Fuels

    Energy Technology Data Exchange (ETDEWEB)

    Fitzgerald, Peter [Global Nuclear Fuels; Laughter, Mark D [ORNL; Martyn, Rose [Global Nuclear Fuels; Richardson, Dave [ORNL; Rowe, Nathan C [ORNL; Pickett, Chris A [ORNL; Younkin, James R [ORNL; Shephard, Adam M [ORNL

    2010-01-01

    Accountability scale data from the Global Nuclear Fuels (GNF) fuel fabrication facility in Wilmington, NC has been collected and analyzed as a part of the Cylinder Accountability and Tracking System (CATS) field trial in 2009. The purpose of the data collection was to demonstrate an authentication method for safeguards applications, and the use of load cell data in cylinder accountability. The scale data was acquired using a commercial off-the-shelf communication server with authentication and encryption capabilities. The authenticated weight data was then analyzed to determine facility operating activities. The data allowed for the determination of the number of full and empty cylinders weighed and the respective weights along with other operational activities. Data authentication concepts, practices and methods, the details of the GNF weight data authentication implementation and scale data interpretation results will be presented.

  8. Authentication and Interpretation of Weight Data Collected from Accountability Scales at Global Nuclear Fuels

    International Nuclear Information System (INIS)

    Accountability scale data from the Global Nuclear Fuels (GNF) fuel fabrication facility in Wilmington, NC has been collected and analyzed as a part of the Cylinder Accountability and Tracking System (CATS) field trial in 2009. The purpose of the data collection was to demonstrate an authentication method for safeguards applications, and the use of load cell data in cylinder accountability. The scale data was acquired using a commercial off-the-shelf communication server with authentication and encryption capabilities. The authenticated weight data was then analyzed to determine facility operating activities. The data allowed for the determination of the number of full and empty cylinders weighed and the respective weights along with other operational activities. Data authentication concepts, practices and methods, the details of the GNF weight data authentication implementation and scale data interpretation results will be presented.

  9. 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.

  10. A future vision of nuclear material information systems

    International Nuclear Information System (INIS)

    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

  11. Illicit trafficking of nuclear material and other radioactive sources

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    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

  13. US/Russian laboratory-to-laboratory program in materials protection, control and accounting at the RRC Kurchatov Institute

    International Nuclear Information System (INIS)

    Six US DOE Laboratories are carrying out a program of cooperation with the Russian Research Center Kurchatov Institute (RRC KI) to improve the capabilities and facilities in nuclear material protection, control, and accounting (MPC ampersand A). In 1995, the primary emphasis of this program was the implementation of improved physical protection at a demonstration building at RRC KI, and the upgrading of the computerized MC ampersand A system, diagnostic instrumentation, and physical inventory procedures at a critical assembly within this building. Work continues in 1996 at the demonstration building but now also has begun at the two Kurchatov buildings which constitute the Central Storage Facility (CSF). At this facility, there will be upgrades in the physical inventory taking procedures, a test and evaluation of gamma-ray isotopic measurements, evaluations of nuclear material portal monitors and neutron-based measurement equipment as well as development of an improved computerized materials accounting system, implementation of bar code printing and reading equipment, development of tamper indicating device program, and substantial improvements in physical protection. Also, vulnerability assessments begun in 1995 are being extended to additional high priority facilities at Kurchatov

  14. Integrated nuclear techniques to detect illicit materials

    Energy Technology Data Exchange (ETDEWEB)

    DeVolpi, A.

    1997-10-01

    This paper discusses the problem of detecting explosives in the context of an object being transported for illicit purposes. The author emphasizes that technologies developed for this particular application have payoffs in many related problem areas. The author discusses nuclear techniques which can be applied to this detection problem. These include: x-ray imaging; neutronic interrogation; inelastic neutron scattering; fieldable neutron generators. He discusses work which has been done on the applications of these technologies, including results for detection of narcotics. He also discusses efforts to integrate these techniques into complementary systems which offer improved performance.

  15. Nuclear energy and materials in the 21st century

    Energy Technology Data Exchange (ETDEWEB)

    Krakowski, R.A.; Davidson, J.W.; Bathke, C.G. [and others

    1997-05-01

    The Global Nuclear Vision Project at the Los Alamos National Laboratory is examining a range of long-term nuclear energy futures as well as exploring and assessing optimal nuclear fuel-cycle and material strategies. An established global energy, economics, environmental (E{sup 3}) model has been adopted and modified with a simplified, but comprehensive and multi-regional, nuclear energy module. Consistent nuclear energy scenarios are constructed, where future demands for nuclear power are projected in price competition with other energy sources under a wide range of long-term ({approx}2100) demographic, economic, policy, and technological drivers. A spectrum of futures is examined at two levels in a hierarchy of scenario attributes in which drivers are either external or internal to nuclear energy. The result reported examine departures from a basis scenario and are presented in the following order of increasing specificity: (a) definition and parametric variations of the basis scenario; (b) comparison of the basis scenario with other recent studies; (c) parametric studies that vary upper-level hierarchical scenario attributes (external drivers); and (d) variations of the lower-level scenario attributes (internal drivers). Impacts of a range of nuclear fuel-cycle scenarios are reflected back to the higher-level scenario attributes that characterize particular nuclear energy scenarios. Special attention is given to the role of nuclear materials inventories (in magnitude, location, and form) and their contribution to the long-term sustainability of nuclear energy, the future competitiveness of both conventional and advanced nuclear reactors, and proliferation risk.

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

    International Nuclear Information System (INIS)

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

  17. THE DEVELOPMENT OF MATERIAL FLOW INFORMATION BASE OF MANAGEMENT AND ACCOUNTING IN THE CONSTRUCTION INDUSTRY

    Directory of Open Access Journals (Sweden)

    Degaltseva Z. V.

    2015-10-01

    Full Text Available This article discusses the problems of using indicators of material flow in the financial accounting management accounting system. The authors have created and described the classification of material costs in building units. It allows solving the problems of object of research specifying within a given material flow and inventory control within a given logistics systems. There are different approaches to the valuation of material costs in the article. An important aspect of measures for the integration development of accounting systems is the adoption of uniform valuation of building materials and structures. It is proved that the most rational combination of these types of records achieved by an adapted classification and measurement of building materials and structures to the conditions of formation of the budget for the project volume of construction works and the reflection of the actual volume of work in the financial accounting system. On the basis of the accounting policies and the organizational structure of the object of investigation of "Kubanstroykompleks" we have identified responsibility centers (sites for costs related to the material flow: Department of logistics and packaging and warehousing, which consists of a central and railroad warehouse

  18. Country Presentation on Illicit Trafficking of Nuclear Materials

    International Nuclear Information System (INIS)

    Assess the role of various agences in Kenya in fighting illicit traficking of nuclear materials. These includes the police, customs, National Council for Science and Technology, Radiation and Protection Board. Gives incidences of trafficking of various materials in Kenya and related activities like the 1998 terrorist attack of American Embassy in Nairobi and the Kikambala Tourist Hotel in Mombasa

  19. Exploration for uranium and other nuclear materials

    International Nuclear Information System (INIS)

    Prospecting and exploration for uranium and other nuclear minerals have one advantage over prospecting for other metals because of their inherent radioactivity. Radioactivity in the earth is not confined solely to these elements but also to radiations coming from cosmic rays and from fallouts from large-scale atomic and nuclear explosions. The primary uranium mineral is uranimite, however, concentrations of other uranium minerals may also lead to an economic deposit. Thorium is about three times more abundant than uranium in the earth's crust. Uranium is practically found in many types of geologic environment it being ubiquitous and very mobile. Uranium deposits are classified in a descriptive manner, owing to lack of basic information as to its origin. These classifications are peneconcordant, for deposits as conglomerates and sandstones, discordant for vein pegmatite and contact metamorphic deposits, concordant for deposits in shales and phosphate rocks, and miscellaneous for deposits in beach and placer sands containing mostly thorium minerals. The different exploration techniques and their associated instrumentations are discussed from a regional scale survey to a detailed survey. To date, only the Larap copper-molybdenum-magnetite deposit at the Paracale district, Camarines Norte in the Philippines, has been found to contain uranium as discrete uraninite grains in the ore mineral assemblage of the deposit

  20. Monte Carlo Simulation Study of a Differential Calorimeter Measuring the Nuclear Heating in Material Testing Reactors

    Science.gov (United States)

    Amharrak, H.; Reynard-Carette, C.; Lyoussi, A.; Carette, M.; Brun, J.; De Vita, C.; Fourmentel, D.; Villard, J.-F.; Guimbal, P.

    2016-02-01

    The nuclear heating measurements in Material Testing Reactors (MTRs) are crucial for the study of nuclear materials and fuels under irradiation. The reference measurements of this nuclear heating are especially performed by a differential calorimeter including a graphite sample material. Then these measurements are used for other materials, other geometries, or other experimental conditions in order to predict the nuclear heating and thermal conditions induced in the irradiation devices. This paper will present new simulations with MCNP Monte-Carlo transport code to determine the gamma heating profile inside the calorimeter. The whole complex geometry of the sensor has been considered. We use as an input source in the model, the photon spectra calculated in various positions of CARMEN-1 irradiation program in OSIRIS reactor. After a description of the differential calorimeter device, the MCNP modeling used for the calculations of radial profile of nuclear heating inside the calorimeter elements will be introduced. The obtained results of different simulations will be detailed and discussed in this paper. The charged particle equilibrium inside the calorimeter elements will be studied. Then we will focus on parametric studies of the various components of the calorimeter. The influence of source type will be also took into account. Moreover the influence of the material used for the sample will be described.

  1. Monte Carlo Simulation Study of a Differential Calorimeter Measuring the Nuclear Heating in Material Testing Reactors

    Directory of Open Access Journals (Sweden)

    Amharrak H.

    2016-01-01

    Full Text Available The nuclear heating measurements in Material Testing Reactors (MTRs are crucial for the study of nuclear materials and fuels under irradiation. The reference measurements of this nuclear heating are especially performed by a differential calorimeter including a graphite sample material. Then these measurements are used for other materials, other geometries, or other experimental conditions in order to predict the nuclear heating and thermal conditions induced in the irradiation devices. This paper will present new simulations with MCNP Monte-Carlo transport code to determine the gamma heating profile inside the calorimeter. The whole complex geometry of the sensor has been considered. We use as an input source in the model, the photon spectra calculated in various positions of CARMEN-1 irradiation program in OSIRIS reactor. After a description of the differential calorimeter device, the MCNP modeling used for the calculations of radial profile of nuclear heating inside the calorimeter elements will be introduced. The obtained results of different simulations will be detailed and discussed in this paper. The charged particle equilibrium inside the calorimeter elements will be studied. Then we will focus on parametric studies of the various components of the calorimeter. The influence of source type will be also took into account. Moreover the influence of the material used for the sample will be described.

  2. Nuclear fuels and materials irradiation technology development in HANARO

    International Nuclear Information System (INIS)

    The equipments for the irradiation tests of nuclear fuels and materials in the HANARO are classified into a capsule and an FTL (Fuel Test Loop). Capsules for irradiation tests of nuclear fuels and materials in HANARO have been developed. Also, extensive efforts have been made to establish the design/manufacturing and irradiation technologies for irradiating nuclear fuels and materials by using these capsules and their control systems, which should be compatible with HANARO's characteristics. Other devices consisting of a fixing of the capsule during an irradiation test in the HANARO, a cutting and a transporting of the capsule main body after an irradiation test were also developed. These capsules and others have been actively utilized for various material irradiation tests requested by users. Based on the accumulated experiences and a user's sophisticated requirements, capsules for a creep test and a fatigue test of materials during an irradiation in HANARO have been developed. And, the irradiation plans related to developing the Gen-IV reactor systems by using capsules in HANARO will mean more emphasis on the development of capsules by focusing on the irradiation tests of materials or nuclear fuels for Gen-IV reactor systems, such as the SFR and the VHTR. The FTL is one of the irradiation devices, which can conduct an irradiation test of a nuclear fuel in HANARO under the operating conditions of commercial nuclear power plants. The 3-test fuel rods can be irradiated in HANARO by using the FTL. The installation of the FTL was completed in March 2007. Currently, the commissioning test of the FTL is being performed. At first the FTL will be used for the irradiation test of an advanced nuclear fuel for a PWR from the end of this year. In this paper, the status and the perspective in the field of material irradiation tests in HANARO are described. (author)

  3. Criteria for Special Nuclear Materials Inventory and Control Procedures

    International Nuclear Information System (INIS)

    One of tile most significant problems that will face investors, managers and operators in nuclear activities and especially in the field of commercial nuclear power, will be the proper control of a nuclear materials inventory that will exceed US $5000 million in value by 1980. Special nuclear materials are expensive when compared to most materials of commerce, e.g. US prices for 90% enriched uranium and 3% enriched uranium as hexafluoride, and for heavy water are $10 808, $254 and $61.60 per kg, respectively. Moreover, in many cases these materials are subjected because of health and safety requirements to special governmental controls not directly related to their monetary value. Despite the high monetary values assigned to these materials, they are destined to be used in large quantity, e.g. some 50- 75 t of 3% enriched material will be used in 500-MW light-water-moderated reactor, and perhaps the equivalent of 200 to 300 reactors of such size will be in operation throughout the world by 1980. Past experience has resulted in the development of special procedures and practice for the commercial control of the large quantity, lower-value materials such as coal or iron ore and for the small quantity, higher value materials such as the precious metals. While they have like prices, special nuclear materials are different in kind and will be handled in quantities much greater than the precious metals. However, while special techniques or special adaptations of old techniques may be necessary, proper use of various established inventory control practices should be sufficient in most cases to protect adequately the investment of nations and individuals in these expensive materials. This paper establishes criteria for materials control. It specifically considers the appropriateness of various techniques of inventory control ranging from annual balancing of book records of receipts and shipments through detailed daily physical inventory in the light of the specific value

  4. Detecting fission from special nuclear material sources

    Science.gov (United States)

    Rowland, Mark S.; Snyderman, Neal J.

    2012-06-05

    A neutron detector system for discriminating fissile material from non-fissile material wherein a digital data acquisition unit collects data at high rate, and in real-time processes large volumes of data directly into information that a first responder can use to discriminate materials. The system comprises counting neutrons from the unknown source and detecting excess grouped neutrons to identify fission in the unknown source. The system includes a graphing component that displays the plot of the neutron distribution from the unknown source over a Poisson distribution and a plot of neutrons due to background or environmental sources. The system further includes a known neutron source placed in proximity to the unknown source to actively interrogate the unknown source in order to accentuate differences in neutron emission from the unknown source from Poisson distributions and/or environmental sources.

  5. Accelerated Nuclear Energy Materials Development with Multiple Ion Beams

    Energy Technology Data Exchange (ETDEWEB)

    Fluss, M J; Bench, G

    2009-08-19

    A fundamental issue in nuclear energy is the changes in material properties as a consequence of time, temperature, and neutron fluence. Usually, candidate materials for nuclear energy applications are tested in nuclear reactors to understand and model the changes that arise from a combination of atomic displacements, helium and hydrogen production, and other nuclear transmutations (e.g. fission and the production of fission products). Experiments may be carried out under neutron irradiation conditions in existing nuclear materials test reactors (at rates of 10 to 20 displacements per atom (DPA) per year or burn-up rates of a few percent per year for fertile fuels), but such an approach takes much too long for many high neutron fluence scenarios (300 DPA for example) expected in reactors of the next generation. Indeed it is reasonable to say that there are no neutron sources available today to accomplish sufficiently rapid accelerated aging let alone also provide the temperature and spectral characteristics of future fast spectrum nuclear energy systems (fusion and fission both). Consequently, materials research and development progress continues to be severely limited by this bottleneck.

  6. Transcending sovereignty. In the management and control of nuclear material

    International Nuclear Information System (INIS)

    Effective control of nuclear material is fundamentally important to the credibility and reliability of the nuclear non-proliferation regime. Under the Treaty on the Non-Proliferation of Nuclear Weapons (NPT), international safeguards are applied to non-nuclear- weapon State Parties for the purpose of verifying compliance with their undertakings not to seek to acquire nuclear weapons or explosive devices by assuring that safeguarded nuclear activities and material are not diverted from their intended peaceful use. Reflecting the sovereign State basis upon which the international system rests, the control and protection of nuclear materials within the State are the responsibility of the national authority. This division of responsibility between international verification of non-diversion on the one hand and national responsibility for material protection on the other has worked quite well over time. But it has not created a seamless web of fully effective control over nuclear material. 34 In so far as safeguards are concerned, six points are to be made: 1. INFCIRC/153 Agreements: Completion by all NPT Parties of the required safeguards agreements with the IAEA. Fifty States Party to the NPT still have not entered into treaty-obligated safeguards agreements with the IAEA. 2. Adherence by all States having full-scope safeguards INFCIRC/540. As noted, very few States have thus far negotiated and implemented the strengthened safeguards arrangements. 3. United Nations Security Council action to take its 1992 assertions (related to compliance and enforcement) on proliferation and safeguards a step further. 4. Non-NPT Party support for international Safeguards. 5. Safeguards financing. 6. IAEA Access to export license information

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

    International Nuclear Information System (INIS)

    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

  8. Safety review and assessment on nuclear fuel cycle installations and nuclear materials control

    International Nuclear Information System (INIS)

    The NNSA conducted a review and assessment, and supervision on the large-sized fuel manufacture line of YNFP and spent fuel storage pool of LNFC and the pilot plant of Spent Fuel Reprocessing. The physical protection of newly constructed nuclear installations were reviewed and assessed and an regulatory inspection was conducted on the units that being granted with a license for nuclear materials

  9. Nuclear Materials Management at the Japan Atomic Energy Research Institute

    International Nuclear Information System (INIS)

    The procedures for nuclear material control are reviewed, based on the experiences at the Japan Atomic Energy Research Institute. Nuclear materials to be discussed here include: - Both natural and enriched uranium for research; - Imported enriched nuclear fuel elements for JRR-2 (10-MW CP-5), JRR-4 (1-MW swimming pool), JPDR (12.5-MW(e) BWR), and the critical assemblies for JMTR (50-MW light-water moderated) and for the propulsion reactor; - Domestically-fabricated natural uranium fuel elements for JRR-3 (10-MW heavy-water moderated); - Domestically-fabricated fuels for the critical assemblies manufactured from imported enriched uranium oxides; - Domestically-fabricated enriched fuel elements for JPDR and for the propulsion reactor manufactured from imported enriched uranium hexafluoride. Both thorium and plutonium are also under control, but excluded from the present paper. Entire administrative pattern for nuclear material control is first presented. The emphasis is placed on the domestic fabrication of enriched fuel elements from imported enriched uranium, and the details of the control procedures during and after the fabrication process are discussed. The control procedures include the chemical analysis for purity check, isotopic assay by mass spectrometry, physical and mechanical tests of fabricated products, and the careful prevention in the diversion of nuclear materials. Administrative problems being attributed to Japanese domestic situation are presented; for example, the segregation, collection and efficient recovery and practical uses of residual uranium from the fabrication process. Methods for keeping records on the storage and uses of nuclear materials are also discussed. More satisfactory control procedures for other nuclear materials such as thorium and heavy water are under progress. (author)

  10. Chemical digestion of low level nuclear solid waste material

    International Nuclear Information System (INIS)

    A method is described for processing low level, light weight, bulky, combustible nuclear solid waste material comprising the steps of reacting said solid waste material with concentrated sulfuric acid at a temperature within the range of 230 deg - 300 deg C and simultaneously, subsequently, or both simultaneously and subsequently contacting said waste with concentrated nitric acid or nitrogen oxides whereby carbonaceous material is oxidized to gaseous byproducts and a low volume residue. (author)

  11. Potential applications of nanostructured materials in nuclear waste management.

    Energy Technology Data Exchange (ETDEWEB)

    Braterman, Paul S. (The University of North Texas, Denton, TX); Phol, Phillip Isabio; Xu, Zhi-Ping (The University of North Texas, Denton, TX); Brinker, C. Jeffrey; Yang, Yi (University of New Mexico, Albuquerque, NM); Bryan, Charles R.; Yu, Kui; Xu, Huifang (University of New Mexico, Albuquerque, NM); Wang, Yifeng; Gao, Huizhen

    2003-09-01

    This report summarizes the results obtained from a Laboratory Directed Research & Development (LDRD) project entitled 'Investigation of Potential Applications of Self-Assembled Nanostructured Materials in Nuclear Waste Management'. The objectives of this project are to (1) provide a mechanistic understanding of the control of nanometer-scale structures on the ion sorption capability of materials and (2) develop appropriate engineering approaches to improving material properties based on such an understanding.

  12. From Governmental Accounting into National Accounts: Adjustments Diversity and Materiality with Evidence from the Iberian Countries’ Central Governments

    Directory of Open Access Journals (Sweden)

    Maria Antónia Jorge de Jesus

    2014-09-01

    Full Text Available In a context where governments around the world acknowledge a need for more informative governmental financial reporting to improve financial sustainability, the European Council is proposing that EU member states adopt International Public Sector Accounting Standards (IPSASs—which are recognized as also allowing improved reliability of government finance statistics—in all subsectors of the General Government Sector (GGS. Consequently, the Governmental Accounting (GA role of running and reporting on governments’ budgets for purposes of decisionmaking and accountability is changing to include being part of the EU budgetary and monetary policy, specifically within the Euro zone. Accordingly, the objective of this paper is twofold. First, it aims to start a debate in the literature about the ability of GA as it stands across Europe to meet the European System of National and Regional Accounts (ESA requirements concerning GGS data. This assumes particular relevance in a context where the two systems have to coexist, but given that budgetary reporting (GA is the main input to ESA reporting (NA, reconciliation between the two systems is required. The second objective is of a more technical nature—empirically demonstrating the diversity and materiality of the main adjustments to be made when converting GGS data from GA into NA. This is done by using evidence for Portugal and Spain, focusing on Central Government data for the period 2006–2009 and measuring their quantitative impact on the public (budgetary deficit. We conclude that GA systems as they are across EU do not meet ESA requirements, and further alignment is therefore needed to reduce adjustments as much as possible when translating data from GA into NA. Additionally, in the case of Portugal and Spain, the main findings show that the adjustments from GA into NA present great diversity for both of these Iberian countries. As for materiality, their impact is greater in Spain, but still

  13. Graphite matrix materials for nuclear waste isolation

    Energy Technology Data Exchange (ETDEWEB)

    Morgan, W.C.

    1981-06-01

    At low temperatures, graphites are chemically inert to all but the strongest oxidizing agents. The raw materials from which artificial graphites are produced are plentiful and inexpensive. Morover, the physical properties of artificial graphites can be varied over a very wide range by the choice of raw materials and manufacturing processes. Manufacturing processes are reviewed herein, with primary emphasis on those processes which might be used to produce a graphite matrix for the waste forms. The approach, recommended herein, involves the low-temperature compaction of a finely ground powder produced from graphitized petroleum coke. The resultant compacts should have fairly good strength, low permeability to both liquids and gases, and anisotropic physical properties. In particular, the anisotropy of the thermal expansion coefficients and the thermal conductivity should be advantageous for this application. With two possible exceptions, the graphite matrix appears to be superior to the metal alloy matrices which have been recommended in prior studies. The two possible exceptions are the requirements on strength and permeability; both requirements will be strongly influenced by the containment design, including the choice of materials and the waste form, of the multibarrier package. Various methods for increasing the strength, and for decreasing the permeability of the matrix, are reviewed and discussed in the sections in Incorporation of Other Materials and Elimination of Porosity. However, it would be premature to recommend a particular process until the overall multi-barrier design is better defined. It is recommended that increased emphasis be placed on further development of the low-temperature compacted graphite matrix concept.

  14. Optoelectronic inventory system for special nuclear material

    Energy Technology Data Exchange (ETDEWEB)

    Sieradzki, F.H.

    1994-01-01

    In support of the Department of Energy`s Dismantlement Program, the Optoelectronics Characterization and Sensor Development Department 2231 at Sandia National Laboratories/New Mexico has developed an in situ nonintrusive Optoelectronic Inventory System (OIS) that has the potential for application wherever periodic inventory of selected material is desired. Using a network of fiber-optic links, the OIS retrieves and stores inventory signatures from data storage devices (which are permanently attached to material storage containers) while inherently providing electromagnetic pulse immunity and electrical noise isolation. Photovoltaic cells (located within the storage facility) convert laser diode optic power from a laser driver to electrical energy. When powered and triggered, the data storage devices sequentially output their digital inventory signatures through light-emitting diode/photo diode data links for retrieval and storage in a mobile data acquisition system. An item`s exact location is determined through fiber-optic network and software design. The OIS provides an on-demand method for obtaining acceptable inventory reports while eliminating the need for human presence inside the material storage facility. By using modularization and prefabricated construction with mature technologies and components, an OIS installation with virtually unlimited capacity can be tailored to the customer`s requirements.

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

    International Nuclear Information System (INIS)

    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 226Ra or 137Cs 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

  16. Nuclear technology cost assessments using G4Econs and its cost accounting system

    International Nuclear Information System (INIS)

    Nuclear energy is back on the agenda worldwide. Third generation nuclear reactors are under construction. On the other hand, the fourth generation of nuclear reactors is on the drawing board. Obviously, one of the most important parameters, influencing the market penetration of any new reactor, is its economic performance. However, as the fourth generation concepts are often in a preliminary stage, a thorough bottom-up cost estimate cannot be made. This paper describes a cost estimating approach that has been developed to provide a top-down cost estimate for future nuclear reactors and their associated fuel cycles. This approach is based on a structured accounting system as applied in the G4-ECONS model which is developed by Economics Modeling Working Group of the Generation IV International Forum (GIF-EMWG). The developed approach is applied to 2 types of Generation IV nuclear reactor designs: a 210 MWe HTR (High Temperature Reactor) and a 1500 MWe SFR (Sodium-cooled Fast reactor). The focus will be on deployment of such reactors in a European context. The approach is largely based on a comparative analysis with more matured Generation III nuclear systems which are under construction today. The comparative cost analysis shows that the 200 MWe HTR specific (Euros/kWe) construction costs are more than 2 times the specific costs of an EPR. The specific construction costs of a 1500 MWe SFR are calculated to be about 60% more than the specific costs of an EPR. It should be noted that the current evaluation is largely based on scaling effects

  17. IAEA concerned about security of nuclear material in Iraq

    International Nuclear Information System (INIS)

    Full text: Several recent media reports have raised concerns about the security of nuclear material stored near the Tuwaitha Nuclear Research Centre in Iraq. U.S. military forces recently entered the Tuwaitha site. The International Atomic Energy Agency (IAEA) asked the United States to ensure that the material located there is properly protected and that access to the site is restricted. The IAEA has subsequently received such assurances. 'I have written yesterday to the United States Government asking that it ensure the security and safety of all the nuclear material there, which has been under IAEA seal since 1991. I indicated that until our inspectors return to Iraq, the U.S. has responsibility for maintaining security at this important storage facility,' said Dr Mohamed ElBaradei, Director General of the IAEA. Most of the nuclear and other radioactive material at Iraq's Tuwaitha Nuclear Research Centre is stored near the main complex in the three buildings which are known as 'Location C.' It contains nuclear material, covered by Iraq's Safeguards Agreement under the NPT, that the Agency was not required by the U.N. Security Council to remove after the Gulf war in 1991 because it could not be used directly for nuclear weapons purposes. A separate building at Location C is used to store radioisotope sources. Radiation levels are high and great care must be taken if entering the building. IAEA inspectors have been monitoring and inspecting the material at Location C periodically since 1991. The IAEA applied seals on the drums containing the nuclear materials and the building itself. 'As soon as circumstances permit, the IAEA should return to verify that there has been no diversion of this material,' said Dr. ElBaradei. During weapons inspections in Iraq from November 2002 until March 2003, IAEA inspectors visited the Tuwaitha research center many times. Inspectors have examined underground areas at Tuwaitha as part of the inspection process, including the

  18. Strategic special nuclear material inventory differences. Semiannual report, October 1, 1983-March 31, 1984

    International Nuclear Information System (INIS)

    This fifteenth periodic semiannual report of Inventory Differences (ID) covers the first six months of fiscal year 1984 (October 1, 1983 through March 31, 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

  19. Electron momentum spectroscopy of aniline taking account of nuclear dynamics in the initial electronic ground state

    Science.gov (United States)

    Farasat, M.; Shojaei, S. H. R.; Morini, F.; Golzan, M. M.; Deleuze, M. S.

    2016-04-01

    The electronic structure, electron binding energy spectrum and (e, 2e) momentum distributions of aniline have been theoretically predicted at an electron impact energy of 1.500 keV on the basis of Born-Oppenheimer molecular dynamical simulations, in order to account for thermally induced nuclear motions in the initial electronic ground state. Most computed momentum profiles are rather insensitive to thermally induced alterations of the molecular structure, with the exception of the profiles corresponding to two ionization bands at electron binding energies comprised between ˜10.0 and ˜12.0 eV (band C) and between ˜16.5 and ˜20.0 eV (band G). These profiles are found to be strongly influenced by nuclear dynamics in the electronic ground state, especially in the low momentum region. The obtained results show that thermal averaging smears out most generally the spectral fingerprints that are induced by nitrogen inversion.

  20. Semiannual report on strategic special nuclear material inventory differences

    International Nuclear Information System (INIS)

    This twentieth periodic semiannual report of unclassified Inventory Differences (ID's) covers the second six months of fiscal year 1986 (April 1, 1986, through September 30, 1986) for all key Department of Energy (DOE) and DOE contractor operated facilities possessing strategic special nuclear materials. Data for the Rocky Flats and Y-12 nuclear weapons production facilities are not included in the report in order to protect classified nuclear weapons information; however, classified ID data from these facilities receive the same scrutiny and analyses as the unclassified data

  1. Study meeting on 'criteria for materials of nuclear fusion reactors'

    International Nuclear Information System (INIS)

    This study meeting was held on March 1 and 2, 1984, at the Institute of Plasma Physics, Nagoya University. Recently, the problems required for the materials of nuclear fusion reactors have become considerably clear. The problem of the high concentration damage due to 14 MeV neutrons and the problem of surface materials have been well known from the beginning, but moreover, the radioactivation of materials, the problem of safety, and the feasibility of remote operation related to it have become urgent problems. Besides, the plan of large scale facilities as the means of promoting research is one of the important themes. The research on materials must take part in the whole technological problems which enable the construction of actual nuclear fusion devices. This study meeting was held as a part of the R project of the Institute of Plasma Physics, Nagoya University, but it aimed at grasping the present status and discussing the future perspective of the materials of nuclear fusion reactors, and examining the criteria for nuclear fusion materials. The gists of 23 lectures presented at the meeting are collected in this report. (Kako, I.)

  2. THE ATTRACTIVENESS OF MATERIALS IN ADVANCED NUCLEAR FUEL CYCLES FOR VARIOUS PROLIFERATION AND THEFT SCENARIOS

    Energy Technology Data Exchange (ETDEWEB)

    Bathke, C. G.; Ebbinghaus, Bartley B.; Collins, Brian A.; Sleaford, Brad W.; Hase, Kevin R.; Robel, Martin; Wallace, R. K.; Bradley, Keith S.; Ireland, J. R.; Jarvinen, G. D.; Johnson, M. W.; Prichard, Andrew W.; Smith, Brian W.

    2012-08-29

    We must anticipate that the day is approaching when details of nuclear weapons design and fabrication will become common knowledge. On that day we must be particularly certain that all special nuclear materials (SNM) are adequately accounted for and protected and that we have a clear understanding of the utility of nuclear materials to potential adversaries. To this end, this paper examines the attractiveness of materials mixtures containing SNM and alternate nuclear materials associated with the plutonium-uranium reduction extraction (Purex), uranium extraction (UREX), coextraction (COEX), thorium extraction (THOREX), and PYROX (an electrochemical refining method) reprocessing schemes. This paper provides a set of figures of merit for evaluating material attractiveness that covers a broad range of proliferant state and subnational group capabilities. The primary conclusion of this paper is that all fissile material must be rigorously safeguarded to detect diversion by a state and must be provided the highest levels of physical protection to prevent theft by subnational groups; no 'silver bullet' fuel cycle has been found that will permit the relaxation of current international safeguards or national physical security protection levels. The work reported herein has been performed at the request of the U.S. Department of Energy (DOE) and is based on the calculation of 'attractiveness levels' that are expressed in terms consistent with, but normally reserved for, the nuclear materials in DOE nuclear facilities. The methodology and findings are presented. Additionally, how these attractiveness levels relate to proliferation resistance and physical security is discussed.

  3. Detection of shielded nuclear material in a cargo container

    International Nuclear Information System (INIS)

    The Idaho National Laboratory, along with Los Alamos National Laboratory and the Idaho State University's Idaho Accelerator Center, are developing electron accelerator-based, photonuclear inspection technologies for the detection of shielded nuclear material within air-, rail-, and especially, maritime-cargo transportation containers. This paper describes a developing prototypical cargo container inspection system utilizing the Pulsed Photonuclear Assessment (PPA) technology, incorporates interchangeable, well-defined, contraband shielding structures (i.e., 'calibration' pallets) providing realistic detection data for induced radiation signatures from smuggled nuclear material, and provides various shielded nuclear material detection results. Using a 4.8-kg quantity of depleted uranium, neutron and gamma-ray detection responses are presented for well-defined shielded and unshielded configurations evaluated in a selected cargo container inspection configuration

  4. Detection of shielded nuclear material in a cargo container

    Science.gov (United States)

    Jones, James L.; Norman, Daren R.; Haskell, Kevin J.; Sterbentz, James W.; Yoon, Woo Y.; Watson, Scott M.; Johnson, James T.; Zabriskie, John M.; Bennett, Brion D.; Watson, Richard W.; Moss, Cavin E.; Frank Harmon, J.

    2006-06-01

    The Idaho National Laboratory, along with Los Alamos National Laboratory and the Idaho State University's Idaho Accelerator Center, are developing electron accelerator-based, photonuclear inspection technologies for the detection of shielded nuclear material within air-, rail-, and especially, maritime-cargo transportation containers. This paper describes a developing prototypical cargo container inspection system utilizing the Pulsed Photonuclear Assessment (PPA) technology, incorporates interchangeable, well-defined, contraband shielding structures (i.e., "calibration" pallets) providing realistic detection data for induced radiation signatures from smuggled nuclear material, and provides various shielded nuclear material detection results. Using a 4.8-kg quantity of depleted uranium, neutron and gamma-ray detection responses are presented for well-defined shielded and unshielded configurations evaluated in a selected cargo container inspection configuration.

  5. On evaluated nuclear data for beta-delayed gamma rays following of special nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Mencarini, Leonardo de H.; Caldeira, Alexandre D., E-mail: mencarini@ieav.cta.b, E-mail: alexdc@ieav.cta.b [Instituto de Estudos Avancados (IEAv/CTA), Sao Jose dos Campos, SP (Brazil)

    2011-07-01

    In this paper, a new type of information available in ENDF is discussed. During a consistency check of the evaluated nuclear data library ENDF/B-VII.0 performed at the Nuclear Data Subdivision of the Institute for Advanced Studies, the size of the files for some materials drew the attention of one of the authors. Almost 94 % of all available information for these special nuclear materials is used to represent the beta-delayed gamma rays following fission. This is the first time this information is included in an ENDF version. (author)

  6. On evaluated nuclear data for beta-delayed gamma rays following of special nuclear materials

    International Nuclear Information System (INIS)

    In this paper, a new type of information available in ENDF is discussed. During a consistency check of the evaluated nuclear data library ENDF/B-VII.0 performed at the Nuclear Data Subdivision of the Institute for Advanced Studies, the size of the files for some materials drew the attention of one of the authors. Almost 94 % of all available information for these special nuclear materials is used to represent the beta-delayed gamma rays following fission. This is the first time this information is included in an ENDF version. (author)

  7. Development of stainless steels for nuclear power plant - Advanced nuclear materials development -

    International Nuclear Information System (INIS)

    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)

  8. 10 CFR 75.33 - Accounting reports.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Accounting reports. 75.33 Section 75.33 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) SAFEGUARDS ON NUCLEAR MATERIAL-IMPLEMENTATION OF US/IAEA AGREEMENT Reports § 75.33 Accounting reports. (a)(1) The accounting reports for each IAEA material balance area...

  9. Safety management on nuclear fuel cycle installations and nuclear material control

    International Nuclear Information System (INIS)

    In 1998, the NNSA conducted some inspections on the YIBIN Nuclear Fuel Fabrication Plant that was under normal operation and the Pilot plant of NPP spent fuel Reprocessing that was construction at the Lanzhou Nuclear Fuel Complex. The NNSA also issued the OP to Tsinghua University for its Fuel Fabrication Laboratory of HTR-10 after safety review. The NNSA conducted the safety review on the CP application for the Fabrication Facility of Fuel Element for Heavy Water Reactor (CANDU-6) at the Baotou Nuclear Fuel Plant of CNNC in Baotou. The NNSA finished the safety review on the Beilong intermediate-level and low-level Radioactive Waste Repository in Guangdong. The NNSA conducted some inspections on the nuclear material control, and completed the verification of the Nuclear Material License of China Corporation of Atomic Energy Industry and other two organizations

  10. 10 CFR 74.59 - Quality assurance and accounting requirements.

    Science.gov (United States)

    2010-01-01

    ... planning, coordinating, and administering material control and accounting functions, independence of... Section 74.59 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Formula Quantities of Strategic Special Nuclear Material § 74.59 Quality assurance...

  11. Progress in the activities on prevention and combating of illicit trafficking of nuclear material in Lithuania

    International Nuclear Information System (INIS)

    Full text: The paper gives a general overview of the progress which has been made in the activities on prevention and combating of illicit trafficking of nuclear material in Lithuania. It describes the measures which were taken to strengthen nuclear material accounting and control and physical protection. The current status of the national legislation and the functions of institutions involved in control of nuclear material and combating of illicit trafficking are discussed. Lithuania, similar to many countries, did not avoid a new type of a crime - smuggling of nuclear materials - which was observed in the 1990's. The most serious case in Lithuania happened in 1993 when fresh fuel assembly was stolen from Ignalina NPP. This assembly contains approximately 124 kg of UO2 (enrichment 2%). 100 kg of the pellets from this assembly was found later in several pieces at different places. This case served as a strong stimulus to strengthen prevention measures of Illicit trafficking. The legal basis was created and governmental institutions were obliged with special duties related with nuclear material. The laws and regulations set the order for the shipment and handling of nuclear material. The penalties for violation of these laws and regulations specified in Penal Code and Administrative Code were made stricter. The State system of accounting for and control of nuclear material (SSAC) is a very important element in prevention of the illicit trafficking. The Regulations of Accounting for and Control of Nuclear Material at Nuclear Facilities and LOFs was issued by the State Nuclear Power Safety Inspectorate (VATESI) on 10 December 1997 following the provisions of the Law on Nuclear Energy. Lithuania extended its international obligations by ratifying the Protocol Additional to the Safeguards Agreement (entered into force on 5 July 2000). The fully computerized nuclear material accountancy system was created at Ignalina NPP. The system gives the possibility to find the

  12. 10 CFR Appendix M to Part 110 - Categorization of Nuclear Material d

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Categorization of Nuclear Material d M Appendix M to Part 110 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL Pt. 110, App. M Appendix M to Part 110—Categorization of Nuclear Material d Material Form...

  13. IAEA inspectors complete verification of nuclear material in Iraq

    International Nuclear Information System (INIS)

    Full text: A team of IAEA inspectors has returned from Iraq to Vienna after completing the annual Physical Inventory Verification of declared nuclear material. The material - natural or low-enriched uranium - is consolidated at a storage facility near the Tuwaitha complex, south of Baghdad. The inspectors found no diversion of nuclear material. The two-day inspection was conducted with the logistical and security assistance of the Multinational Force, the Office of the UN Security Coordinator, and the UN Assistance Mission for Iraq. Every non-nuclear-weapon State party to the NPT that has declared holdings of nuclear material is required to undergo such inspections. The inspectors verify the correctness of the State's declaration, and that material has not been diverted to any undeclared activity. Such inspections have been performed in Iraq on a continuing basis. NPT safeguards inspections are limited in scope and coverage as compared to the verification activities carried out in 1991-98 and 2002-03 by the IAEA under Security Council resolution 687 and related resolutions. (IAEA)

  14. Material development for India’s nuclear power programme

    Indian Academy of Sciences (India)

    A K Suri

    2013-10-01

    The area of materials research has registered a phenomenal growth in the recent years, assiduously accepting and assimilating ideas, concepts and analytical as well as experimental methodologies and techniques form almost all scientific disciplines, thereby demonstrating its remarkably multidisciplinary and interdisciplinary character. The focus of the materials programme of this centre is to provide materials, processes and processing solutions to the emerging needs of evolving indigenous nuclear energy systems by proactive research and development on a continuing basis. The initial stage of our activities was formulated around three stage Indian nuclear power programme. In stage I, material issues related to in-core materials with emphasis on development of fabrication routes of zirconium alloys for structural application were addressed. Subsequently the thrust areas were development and characterization of mixed oxide fuel, advanced zirconium alloys, structural steels, superalloys, neutron absorber materials based on boron carbides and borides, and shape memory alloys. The research was useful for in-service performance evaluation, safety assessment, residual life estimation and life extension of nuclear reactors built during stage I i.e., PHWRs and BWRs. It also included developments which would permit rapid expansion of nuclear power initially through fast breeder reactor based on mixed oxide fuel and later based on metallic fuels. For the 3rd stage, multilayer coatings, graphite coolant tube, BeO, refractory metals and alloys, heat-treated zirconium alloys are being developed for CHTR, ADSS and AHWR. The materials being developed for fusion programme are low Z and high Z material for plasma facing application, Cu-alloys for heat sink, austenitic steels, RAFMS and ODS for structurals and NbTi, Nb3Sn and Nb3Al superconductors, lithium titanate, lithium silicate breeders, and Pb–Bi coolant. A brief overview of the materials research activities currently being

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

    International Nuclear Information System (INIS)

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

  16. Materials research in support of nuclear power generation

    Energy Technology Data Exchange (ETDEWEB)

    Jackman, J. [Natural Resources Canada, Ottawa, Ontario (Canada)

    2011-07-01

    This presentation outlines the activities of CANMET-MTL in materials research in support of nuclear power generation. CANMET-MTL is a Government of Canada research laboratory specializing in materials (metals and metal-based materials). Its mandate is to improve the competitive, social and environmental performance of Canadian industries in the area of metals. These include the economic benefits from value-added processing and manufacturing, materials for clean energy production and improved energy efficiency in processing and product end-use.

  17. Nuclear Security Recommendations on Radioactive Material and Associated Facilities: Recommendations

    International Nuclear Information System (INIS)

    The purpose of this publication is to provide guidance to States and competent authorities on how to develop or enhance, implement and maintain a nuclear security regime for facilities dealing with radioactive material and associated activities. This is to be achieved through the establishment or improvement of their capabilities to implement a legislative and regulatory framework to address the security of radioactive material, associated facilities and associated activities in order to reduce the likelihood of malicious acts involving those materials. These recommendations reflect a broad consensus among States on the requirements which should be met for the security of radioactive material, associated facilities and activities.

  18. Development of Curricula for Nuclear Radiation Protection, Nuclear Instrumentation, and Nuclear Materials Processing Technologies. Final Report.

    Science.gov (United States)

    Hull, Daniel M.

    A study was conducted to assist two-year postsecondary educational institutions in providing technical specialty courses for preparing nuclear technicians. As a result of project activities, curricula have been developed for five categories of nuclear technicians and operators: (1) radiation protection technician, (2) nuclear instrumentation and…

  19. 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.

  20. Basic research for nuclear energy. y Study on the nuclear materials technology

    International Nuclear Information System (INIS)

    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

  1. Search of new scintillation materials for nuclear medicine application

    CERN Document Server

    Korzhik, M V

    2000-01-01

    Oxide crystals have a great potential to develop new advanced scintillation materials which are dense, fast, and bright. This combination of parameters, when combined to affordable price, gives a prospect for materials to be applied in nuclear medicine devices. Some of them have been developed for the last two decades along the line of rear-earth (RE) garnet (RE/sub 3/Al/sub 5/O/sub 12/) oxiorthosilicate (RE/sub 2/SiO/sub 5/) and perovskite (REAlO/sub 3/) crystals doped with Ce ions. Among recently developed oxide materials the lead tungstate scintillator (PWO) becomes the most used scintillation material in high energy physics experiments due to its application in CMS and ALICE experiments at LHC. In this paper we discuss scintillation properties of some new heavy compounds doped with Ce as well as light yield improvement of PWO crystals to apply them in low energy physics and nuclear medicine. (18 refs).

  2. Nuclear reactions and self-shielding effects of gamma-ray database for nuclear materials

    International Nuclear Information System (INIS)

    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)

  3. IMPACT OF NUCLEAR MATERIAL DISSOLUTION ON VESSEL CORROSION

    Energy Technology Data Exchange (ETDEWEB)

    Mickalonis, J.; Dunn, K.; Clifton, B.

    2012-10-01

    Different nuclear materials require different processing conditions. In order to maximize the dissolver vessel lifetime, corrosion testing was conducted for a range of chemistries and temperature used in fuel dissolution. Compositional ranges of elements regularly in the dissolver were evaluated for corrosion of 304L, the material of construction. Corrosion rates of AISI Type 304 stainless steel coupons, both welded and non-welded coupons, were calculated from measured weight losses and post-test concentrations of soluble Fe, Cr and Ni.

  4. Phase field modeling of microstructure evolution in nuclear materials

    International Nuclear Information System (INIS)

    The paper presents two examples of phase field modeling of microstructure evolution of materials used in nuclear power industry. In the first example, an elasto-plastic phase field model was developed to predict hydrogen diffusion, hydride precipitation and fracture in zirconium at crack and notch tips. In the second example, some preliminary results of our current research on void lattice formation in irradiated materials will be given

  5. Preparation of nuclear materials for transmission electron microscopy (TEM)

    International Nuclear Information System (INIS)

    Preparation of highly radioactive and irradiated nuclear fuels and materials for transmission electron microscopy (TEM) is conjoined with a set of unique challenges, including but not limited to personnel radiation exposure and contamination. The paper evaluates three specimen preparation techniques for preparation of irradiated materials and determines which technique yields to the most reliable characterization of radiation damage microstructure. Various specimen preparation artifacts associated with each technique are considered and ways of minimizing these artifacts are delineated.

  6. Technology Readiness Levels for Advanced Nuclear Fuels and Materials Development

    Energy Technology Data Exchange (ETDEWEB)

    Jon Carmack

    2014-01-01

    The Technology Readiness Level (TRL) process is used to quantitatively assess the maturity of a given technology. The TRL process has been developed and successfully used by the Department of Defense (DOD) for development and deployment of new technology and systems for defense applications. In addition, NASA has also successfully used the TRL process to develop and deploy new systems for space applications. Advanced nuclear fuels and materials development is a critical technology needed for closing the nuclear fuel cycle. Because the deployment of a new nuclear fuel forms requires a lengthy and expensive research, development, and demonstration program, applying the TRL concept to the advanced fuel development program is very useful as a management and tracking tool. This report provides definition of the technology readiness level assessment process as defined for use in assessing nuclear fuel technology development for the Advanced Fuel Campaign (AFC).

  7. Behavior of nuclear materials irradiated with a dual ion beam

    Science.gov (United States)

    Thomé, Lionel; Velişa, Gihan; Debelle, Aurélien; Miro, Sandrine; Garrido, Frédérico; Trocellier, Patrick; Serruys, Yves

    2014-05-01

    Synergistic effects of nuclear (Sn) and electronic (Se) energy losses are investigated by comparing the damage accumulated in selected oxide (c-ZrO2, MgO, Gd2Ti2O7) and carbide (SiC) single crystals irradiated with single and dual low and high energy ion beams. Channeling results show that the Sn/Se synergy induces a strong decrease of the damage in MgO and SiC (where amorphization is prevented) and almost no effects in c-ZrO2 and Gd2Ti2O7. Raman and TEM results confirm this statement. The healing of defects generated by nuclear collisions in MgO and SiC is due to the electronic excitation produced in the wake of swift ions. These results present a strong interest for technological applications in the nuclear industry where expected cooperative Sn/Se effects may preserve the integrity of nuclear materials.

  8. ADVANCED CERAMIC MATERIALS FOR NEXT-GENERATION NUCLEAR APPLICATIONS

    Energy Technology Data Exchange (ETDEWEB)

    Marra, J.

    2010-09-29

    , and proliferation), the worldwide community is working to develop and deploy new nuclear energy systems and advanced fuel cycles. These new nuclear systems address the key challenges and include: (1) extracting the full energy value of the nuclear fuel; (2) creating waste solutions with improved long term safety; (3) minimizing the potential for the misuse of the technology and materials for weapons; (4) continually improving the safety of nuclear energy systems; and (5) keeping the cost of energy affordable.

  9. Long Duration Hot Hydrogen Exposure of Nuclear Thermal Rocket Materials

    Science.gov (United States)

    Litchford, Ron J.; Foote, John P.; Hickman, Robert; Dobson, Chris; Clifton, Scooter

    2007-01-01

    An arc-heater driven hyper-thermal convective environments simulator was recently developed and commissioned for long duration hot hydrogen exposure of nuclear thermal rocket materials. This newly established non-nuclear testing capability uses a high-power, multi-gas, wall-stabilized constricted arc-heater to .produce high-temperature pressurized hydrogen flows representative of nuclear reactor core environments, excepting radiation effects, and is intended to serve as a low cost test facility for the purpose of investigating and characterizing candidate fuel/structural materials and improving associated processing/fabrication techniques. Design and engineering development efforts are fully summarized, and facility operating characteristics are reported as determined from a series of baseline performance mapping runs and long duration capability demonstration tests.

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

    International Nuclear Information System (INIS)

    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

  11. Methodology for characterizing potential adversaries of Nuclear Material Safeguards Systems

    International Nuclear Information System (INIS)

    The results are described of a study by Woodward--Clyde Consultants to assist the University of California Lawrence Livermore Laboratory in the development of methods to analyze and evaluate Nuclear Material Safeguards (NMS) Systems. The study concentrated on developing a methodology to assist experts in describing, in quantitative form, their judgments about the characteristics of potential adversaries of NMS Systems

  12. Program strategy document for the Nuclear Materials Transportation Technology Center

    International Nuclear Information System (INIS)

    A multiyear program plan is presented which describes the program of the Nuclear Materials Transportation Technology Center (TIC) at Sandia Laboratories. The work element plans, along with their corresponding work breakdown structures, are presented for TTC activities in the areas of Technology and Information Center, Systems Development, Technology, and Institutional Issues for the years from 1979 to 1985

  13. Methodology for characterizing potential adversaries of Nuclear Material Safeguards Systems

    Energy Technology Data Exchange (ETDEWEB)

    Kirkwood, C.W.; Pollock, S.M.

    1978-11-01

    The results are described of a study by Woodward--Clyde Consultants to assist the University of California Lawrence Livermore Laboratory in the development of methods to analyze and evaluate Nuclear Material Safeguards (NMS) Systems. The study concentrated on developing a methodology to assist experts in describing, in quantitative form, their judgments about the characteristics of potential adversaries of NMS Systems.

  14. Development of proactive technology against nuclear materials degradation

    International Nuclear Information System (INIS)

    As the nuclear power plants are getting older, the extent of materials degradation increases and unexpected degradation mechanisms may occur under complex environments, including high-temperature and pressure, radiation and coolant. The components in the primary system are maintained at the temperature of 320 .deg. C, pressure of 2500 psi, and reactor internals are exposed to fast neutrons. The pipes and nozzles are affected by the mechanical, thermal and corrosive cyclic fatigue stresses. Since the steam generator tubes are affected by both primary and secondary coolants, the materials degradation mechanisms are dependent upon the multiple or complex factors. In this report, we make contribution to the enhancement of reactor safety by developing techniques for predicting and evaluating materials behaviors in nuclear environments. The research product in the following five areas, described in this report, plays a vital role in improving the safe operation of nuclear reactors, upgrading the level of skills and extending the use of nuclear power. Development of corrosion control and protection technology Development of fracture mechanical evaluation model of reactor pressure Development of prediction and analysis technology for radiation damage Development of advanced diagnostic techniques for micro-materials degradation Development of core technology for control of steam generator degradation

  15. The new context for transport of radioactive nuclear material

    Energy Technology Data Exchange (ETDEWEB)

    Anne, Catherine; Galtier, Jerome [Transnucleaire, F-75008 Paris (France)

    2001-07-01

    The transportation of radioactive and nuclear materials, involves all modes of transportation (road, air, sea, rail) with predominance for road and for air (air for radioisotopes). In this paper we examine the impact of new evolutions in the fields of safety, security, logistics means, public acceptance and quality assurance.

  16. 48 CFR 970.4402-4 - Nuclear material transfers.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Nuclear material transfers. 970.4402-4 Section 970.4402-4 Federal Acquisition Regulations System DEPARTMENT OF ENERGY AGENCY... is always accomplished, while at the same time minimizing any advantage one party may have over...

  17. Barcode Automation (BCAuto) for Los Alamos Material Control and Accountability System

    Energy Technology Data Exchange (ETDEWEB)

    Martinez, Benny J [Los Alamos National Laboratory; Chang, Hee Jin [Los Alamos National Laboratory

    2012-06-04

    The plutonium facility is actively processing material on a daily basis at LANL (4000-5000 transactions/month): (1) Physical operations, material transformations, material mixing, splitting, etc.; and (2) Electronic manipulations resulting primarily from updated NDA measurements. Improvements in efficiency and effectiveness are essential due to impacts of recent Voluntary Separation Program and the need to meet mission requirements with fewer personnel. New storage requirements (DOE M 441.1-1, Nuclear Material Packaging Manual) to protect worker safety require tracking of material and its corresponding container over long periods of time. Material at Risk tracking is essential to protect public safety and to ensure continuous operations to meet national security mission needs.

  18. Barcode Automation (BCAuto) for Los Alamos Material Control and Accountability System

    International Nuclear Information System (INIS)

    The plutonium facility is actively processing material on a daily basis at LANL (4000-5000 transactions/month): (1) Physical operations, material transformations, material mixing, splitting, etc.; and (2) Electronic manipulations resulting primarily from updated NDA measurements. Improvements in efficiency and effectiveness are essential due to impacts of recent Voluntary Separation Program and the need to meet mission requirements with fewer personnel. New storage requirements (DOE M 441.1-1, Nuclear Material Packaging Manual) to protect worker safety require tracking of material and its corresponding container over long periods of time. Material at Risk tracking is essential to protect public safety and to ensure continuous operations to meet national security mission needs.

  19. Nuclear fission as a tool to contrast the contraband of special nuclear material

    Indian Academy of Sciences (India)

    Viesti Giuseppe; Cester Davide; Nebbia Giancarlo; Stevanato Luca; Neri Francesco; Petrucci Stefano; Selmi Simone; Tintori Carlo

    2015-09-01

    An integrated mobile system for port security is presented. The system was designed to perform passive measurements of neutrons and -rays to search and identify radioactive and special nuclear materials as well as for the active investigations by using the tagged neutron inspection technique of suspect dangerous materials. The discrimination between difficult-to-detect uranium samples and high materials as lead was specifically studied. The system has been employed in laboratory detection tests and in a seaport field test.

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

    International Nuclear Information System (INIS)

    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)

  1. IMPROVED TECHNNOLOGY TO PREVENT ILLICIT TRAFFICKING IN NUCLEAR MATERIALS

    Energy Technology Data Exchange (ETDEWEB)

    Richardson, J H

    2005-07-20

    The proliferation of nuclear, chemical, and biological weapons (collectively known as weapons of mass destruction, or WMD) and the potential acquisition and use of WMD against the world by terrorists are extremely serious threats to international security. These threats are complex and interrelated. There are myriad routes to weapons of mass destruction--many different starting materials, material sources, and production processes. There are many possible proliferators--threshold countries, rogue states, state-sponsored or transnational terrorists groups, domestic terrorists, and even international crime organizations. Motives for acquiring and using WMD are similarly wide ranging--from a desire to change the regional power balance, deny access to a strategic area, or alter international policy to extortion, revenge, or hate. Because of the complexity of this threat landscape, no single program, technology, or capability--no silver bullet--can solve the WMD proliferation and terrorism problem. An integrated program is needed that addresses the WMD proliferation and terrorism problem from end to end, from prevention to detection, reversal, and response, while avoiding surprise at all stages, with different activities directed specifically at different types of WMD and proliferators. Radiation detection technologies are an important tool in the prevention of proliferation. A variety of new developments have enabled enhanced performance in terms of energy resolution, spatial resolution, predictive modeling and simulation, active interrogation, and ease of operation and deployment in the field. The radiation properties of nuclear materials, particularly highly enriched uranium (HEU), make the detection of smuggled nuclear materials technically difficult. A number of efforts are under way to devise improved detector materials and instruments and to identify novel signatures that could be detected. Key applications of this work include monitoring for radioactive

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

    OpenAIRE

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

    2016-01-01

    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 act...

  3. Executive summary of the special safeguards study on material control and accounting systems. Final report

    International Nuclear Information System (INIS)

    This report assesses the feasibility of real-time systems applied to mixed-oxide fuel rod fabrication. Their interaction with other material control and accounting measures are considered. Economics, effectiveness, and acceptance factors are discussed. A cost-benefit evaluation is made and recommendations given for safeguards improvements

  4. 78 FR 71532 - Amendments to Material Control and Accounting Regulations and Proposed Guidance for Fuel Cycle...

    Science.gov (United States)

    2013-11-29

    ...: I. Background On November 8, 2013 (78 FR 67225; NRC-2009-0096), the NRC published for public comment a proposed rule to amend its regulations for MC&A of SNM. Also on November 8, 2013 (78 FR 67224; NRC... Control and Accounting Regulations and Proposed Guidance for Fuel Cycle Facility Material Control...

  5. Framework for the systematic assessment of a material control and accounting system

    Energy Technology Data Exchange (ETDEWEB)

    Schechter, R.S.; Sacks, I.J.

    1981-04-22

    Procedures are described for the systematic assessment of a Material Control and Accounting (MC and A) system, in terms of compliance to the proposed MC and A Upgrade Rule. The applicability of these assessment procedures to specific Rule provisions is discussed. Special attention is given to the statistical performance of individual subsystems, and their vulnerability to compromise by insider collusion.

  6. Accounting and control of sources of ionising radiation and radioactive materials

    International Nuclear Information System (INIS)

    The paper describes the various elements of the state accounting and control system of radioactive materials and radioactive waste in the Russian Federation, and some of the tasks to be carried out for the development and improvement of the system. A list and short description of documents of this system and structure and the organisation scheme of the system are also presented. (author)

  7. Accounting and control of sources of ionising radiation and radioactive materials

    Energy Technology Data Exchange (ETDEWEB)

    Shatalov, V.V. [All-Russian Scientific Research Institute of Chemical Technology, Moscow (Russian Federation)]. E-mail: shatalov@vniiht.ru; Brykin, S.N.; Serebryakov, I.S. [All-Russian Scientific Research Institute of Chemical Technology, Moscow (Russian Federation); Ershov, V.N.; Glushak, N.S. [Emergency Response Center of Rosatom, Saint-Petersburg (Russian Federation)

    2006-07-01

    The paper describes the various elements of the state accounting and control system of radioactive materials and radioactive waste in the Russian Federation, and some of the tasks to be carried out for the development and improvement of the system. A list and short description of documents of this system and structure and the organisation scheme of the system are also presented. (author)

  8. Framework for the systematic assessment of a material control and accounting system

    International Nuclear Information System (INIS)

    Procedures are described for the systematic assessment of a Material Control and Accounting (MC and A) system, in terms of compliance to the proposed MC and A Upgrade Rule. The applicability of these assessment procedures to specific Rule provisions is discussed. Special attention is given to the statistical performance of individual subsystems, and their vulnerability to compromise by insider collusion

  9. Nuclear-waste-package materials degradation modes and accelerated testing

    International Nuclear Information System (INIS)

    This report reviews the materials degradation modes that may affect the long-term behavior of waste packages for the containment of nuclear waste. It recommends an approach to accelerated testing that can lead to the qualification of waste package materials in specific repository environments in times that are short relative to the time period over which the waste package is expected to provide containment. This report is not a testing plan but rather discusses the direction for research that might be considered in developing plans for accelerated testing of waste package materials and waste forms

  10. Cement-Based Materials for Nuclear Waste Storage

    CERN Document Server

    Cau-di-Coumes, Céline; Frizon, Fabien; Lorente, Sylvie

    2013-01-01

    As the re-emergence of nuclear power as an acceptable energy source on an international basis continues, the need for safe and reliable ways to dispose of radioactive waste becomes ever more critical. The ultimate goal for designing a predisposal waste-management system depends on producing waste containers suitable for storage, transportation and permanent disposal. Cement-Based Materials for Nuclear-Waste Storage provides a roadmap for the use of cementation as an applied technique for the treatment of low- and intermediate-level radioactive wastes.Coverage includes, but is not limited to, a comparison of cementation with other solidification techniques, advantages of calcium-silicate cements over other materials and a discussion of the long-term suitability and safety of waste packages as well as cement barriers. This book also: Discusses the formulation and production of cement waste forms for storing radioactive material Assesses the potential of emerging binders to improve the conditioning of problemati...

  11. Estimating Attributes of Nuclear Weapon and Other Fissile Material Configuration Using Features Of Nuclear Materials Identification Signatures

    International Nuclear Information System (INIS)

    This brief describes a strategy that, when implemented, will allow the attributes, i.e., the physical properties, of nuclear weapon and other configurations of fissile material to be estimated from Nuclear Material Identification System (NMIS) signatures for arms control, treaty verification, and transparency purposes. Attributes are estimated by condensing measured NMIS signatures into ''features'' that approximately represent physical characteristics of the measurement such as gamma-ray transmission, induced fission, etc. The features are obtained from NMIS signatures to estimate quantities related to gamma and neutron transmission through the inspected item and gamma and neutron scattering and production via induced fission within the inspected item. Multivariate, i.e., multiple-feature, linear models have been successfully employed to estimate attributes, and multivariate nonlinear models are currently under investigation. Attributes estimated employing this strategy can then be examined to test the supposition that the inspected item is in fact a nuclear weapon

  12. 10 CFR 110.9 - List of Nuclear Material under NRC export licensing authority.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false List of Nuclear Material under NRC export licensing authority. 110.9 Section 110.9 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL General Provisions § 110.9 List of Nuclear Material under NRC export...

  13. Role of the Materials Review Board and the nuclear waste materials handbook

    International Nuclear Information System (INIS)

    The US Department of Energy has established an organizational structure that assures the quality of key data identified as being important to the licensing of a nuclear waste repository by the US Nuclear Regulatory Commission. The Materials Characterization Center collects and/or develops the test methods needed to obtain the data, and acts as a clearinghouse for all data obtained by the methods, regardless of source. The Materials Review Board reviews both test methods and test data submitted to it, and approves them if they meet the rigorous criteria and standards that have been established. The appearance of test methods and test data in the Nuclear Waste Materials Handbook is evidence that the material has undergone intensive review and can be used with confidence within the bounds of the application specified. The principal use of the Handbook is in the repository licensing process

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

    International Nuclear Information System (INIS)

    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

  15. 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.

  16. Used nuclear materials at Savannah River Site: asset or waste?

    International Nuclear Information System (INIS)

    The nuclear industry, both in the commercial and the government sectors, has generated large quantities of material that span the spectrum of usefulness, from highly valuable ''assets'' to worthless ''wastes''. In many cases, the decision parameters are clear. Transuranic waste and high level waste, for example, have no value, and is either in a final disposition path today, or - in the case of high level waste - awaiting a policy decision about final disposition. Other materials, though discardable, have intrinsic scientific or market value that may be hidden by the complexity, hazard, or cost of recovery. An informed decision process should acknowledge the asset value, or lack of value, of the complete inventory of materials, and the structure necessary to implement the range of possible options. It is important that informed decisions are made about the asset value for the variety of nuclear materials available. For example, there is a significant quantity of spent fuel available for recycle (an estimated $4 billion value in the Savannah River Site's (SRS) L area alone); in fact, SRS has already blended down more than 300 metric tons of uranium for commercial reactor use. Over 34 metric tons of surplus plutonium is also on a path to be used as commercial fuel. There are other radiological materials that are routinely handled at the site in large quantities that should be viewed as strategically important and / or commercially viable. In some cases, these materials are irreplaceable domestically, and failure to consider their recovery could jeopardize our technological leadership or national defense. The inventories of nuclear materials at SRS that have been characterized as ''waste'' include isotopes of plutonium, uranium, americium, and helium. Although planning has been performed to establish the technical and regulatory bases for their discard and disposal, recovery of these materials is both economically attractive and in the national interest.

  17. USED NUCLEAR MATERIALS AT SAVANNAH RIVER SITE: ASSET OR WASTE?

    Energy Technology Data Exchange (ETDEWEB)

    Magoulas, V.

    2013-06-03

    The nuclear industry, both in the commercial and the government sectors, has generated large quantities of material that span the spectrum of usefulness, from highly valuable (“assets”) to worthless (“wastes”). In many cases, the decision parameters are clear. Transuranic waste and high level waste, for example, have no value, and is either in a final disposition path today, or – in the case of high level waste – awaiting a policy decision about final disposition. Other materials, though discardable, have intrinsic scientific or market value that may be hidden by the complexity, hazard, or cost of recovery. An informed decision process should acknowledge the asset value, or lack of value, of the complete inventory of materials, and the structure necessary to implement the range of possible options. It is important that informed decisions are made about the asset value for the variety of nuclear materials available. For example, there is a significant quantity of spent fuel available for recycle (an estimated $4 billion value in the Savannah River Site’s (SRS) L area alone); in fact, SRS has already blended down more than 300 metric tons of uranium for commercial reactor use. Over 34 metric tons of surplus plutonium is also on a path to be used as commercial fuel. There are other radiological materials that are routinely handled at the site in large quantities that should be viewed as strategically important and / or commercially viable. In some cases, these materials are irreplaceable domestically, and failure to consider their recovery could jeopardize our technological leadership or national defense. The inventories of nuclear materials at SRS that have been characterized as “waste” include isotopes of plutonium, uranium, americium, and helium. Although planning has been performed to establish the technical and regulatory bases for their discard and disposal, recovery of these materials is both economically attractive and in the national

  18. Overview of materials technologies for space nuclear power and propulsion

    Science.gov (United States)

    Zinkle, S. J.; Ott, L. J.; Ingersoll, D. T.; Ellis, R. J.; Grossbeck, M. L.

    2002-01-01

    A wide range of different space nuclear systems are currently being evaluated as part of the DOE Special Purpose Fission Technology program. The near-term subset of systems scheduled to be evaluated range from 50 kWe gas-, pumped liquid metal-, or liquid metal heat pipe-cooled reactors for space propulsion to 3 kWe heat pipe or pumped liquid metal systems for Mars surface power applications. The current status of the materials technologies required for the successful development of near-term space nuclear power and propulsion systems is reviewed. Materials examined in this overview include fuels (UN, UO2, UZrH), cladding and structural materials (stainless steel, superalloys, refractory alloys), neutron reflector materials (Be, BeO), and neutron shield materials (B4C,LiH). The materials technologies issues are considerably less demanding for the 3 kWe reactor systems due to lower operating temperatures, lower fuel burnup, and lower radiation damage levels. A few reactor subcomponents in the 3 kWe reactors under evaluation are being used near or above their engineering limits, which may adversely affect the 5 to 10 year lifetime design goal. It appears that most of these issues for the 3 kWe reactor systems can be accommodated by incorporating a few engineering design changes. Design limits (temperature, burnup, stress, radiation levels) for the various materials proposed for space nuclear reactors will be summarized. For example, the temperature and stress limits for Type 316 stainless steel in the 3 kWe Na-cooled heat pipe reactor (Stirling engine) concept will be controlled by thermal creep and CO2 corrosion considerations rather than radiation damage issues. Conversely, the lower operating temperature limit for the LiH shield material will likely be defined by ionizing radiation damage (radiolysis)-induced swelling, even for the relatively low radiation doses associated with the 3 kWe reactor. .

  19. Radiant business. Hazards of international, illicit trafficking with nuclear materials

    International Nuclear Information System (INIS)

    Since the Cold War has been terminated, public media increasingly come out with reports about cases of illicit trafficking with nuclear technology and nuclear materials. So far, the potential hazard has not been exploding into the big disaster, but imagine what may happen if uranium or plutonium falls into the hands of terrorists, fanatics, or Mafia-type organisations ? The author has been investigating into this problem on behalf of the Secretary General of the UN. He has been travelling all around the world in pursuit of information and indications, and now presents us with the essential results of his mission, compiled in this explosive report. (orig./HP)

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

    International Nuclear Information System (INIS)

    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