Illicit diversion of nuclear materials

International Nuclear Information System (INIS)

Bett, F.L.

1975-08-01

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

Concepts of IAEA nuclear materials accounting

International Nuclear Information System (INIS)

Oakberg, John A.

2001-01-01

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

Technical Memory 2010. Nuclear Regulatory Authority

International Nuclear Information System (INIS)

2010-01-01

The technical memory 2010 of the Nuclear Regulatory Authority of Argentine Republic, compile the papers published in the subject on radiation protection and nuclear safety presented in journals, technical reports, congress or meetings of these subjects by the ARN personnel during 2010. In this edition the documents are presented on: environmental protection; safety transport of radioactive materials; regulations; licensing of medical installations; biological radiation effects; therapeutic uses of ionizing radiation and radioprotection of patients; internal dosimetry; radioactive waste management [es

Technical Memory 2011. Nuclear Regulatory Authority

International Nuclear Information System (INIS)

2011-01-01

The technical memory 2011 of the Nuclear Regulatory Authority of Argentine Republic, compile the papers published in the subject on radiation protection and nuclear safety presented in journals, technical reports, congress or meetings of these subjects by the ARN personnel during 2011. In this edition the documents are presented on: environmental protection; safety transport of radioactive materials; regulations; licensing of medical installations; biological radiation effects; therapeutic uses of ionizing radiation and radioprotection of patients; internal dosimetry; radioactive waste management [es

Nuclear Regulatory Authority of the Slovak Republic. Annual Report 1999

International Nuclear Information System (INIS)

Seliga, M.

2000-01-01

A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic in 1999 is presented. These activities are reported under the headings: (1) Foreword; (2) Mission of the Nuclear Regulatory Authority; (3) Legislation; (4) Assessment and inspection of safety at nuclear installations; (4) Safety analyses; (5) Nuclear materials; (6) Radioactive waste; (7) Quality assurance; (8) Personnel qualification and training; (9) Emergency preparedness; (10) International co-operation; (11) Public information; (12) Conclusions; (13) Appendices: Economic and personnel data; Abbreviations; The International nuclear event scales - INES

Thermodynamics of nuclear materials

International Nuclear Information System (INIS)

1979-01-01

conditions. There was also a session on accident analysis, a very important topic in today's nuclear technology. Other topics related to fission reactor technology included thermodynamics in waste management and fuel reprocessing. One severe limitation to scientists working in applied thermodynamics has been the lack of basic or fundamental thermodynamic data. Accordingly, several sessions of the Symposium were devoted to basic data on nuclear fuels as well as fundamental data on the thermodynamic properties of nuclear materials. The Symposium was indeed a timely one. It served as a mechanism by which the participants gained a comprehensive and complete picture of the current status of international thermodynamic investigations on nuclear materials. The data presented at the Symposium is not the final answer to nuclear material problems, but it will serve as a guide for further investigations. (author)

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

International Nuclear Information System (INIS)

Valeca, S.; Valeca, M.

2012-01-01

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

Approaches to characterization of nuclear material for establishment of nuclear forensics

International Nuclear Information System (INIS)

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

2014-01-01

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

Development of nuclear material accountancy control system

International Nuclear Information System (INIS)

Hirosawa, Naonori; Kashima, Sadamitsu; Akiba, Mitsunori

1992-01-01

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

Nuclear Regulatory Authority of the Slovak Republic. Annual Report 2000

International Nuclear Information System (INIS)

Seliga, M.

2001-01-01

A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic in 2000 is presented. These activities are reported under the headings: (1) Foreword and organisation structure; (2) Mission of the Nuclear Regulatory Authority; (3) Legislation; (4) Assessment and inspection of nuclear installations; (5) Safety analyses; (6) Nuclear materials and physical protection of nuclear installations; (7) Radioactive waste; (8) Quality assurance; (9) Personnel qualification and training; (10) Emergency preparedness; (11) International co-operation; (12) Public information; (13) Personnel and economic data of the UJD; (14) Conclusion; (15) Attachments: Abbreviations; Radiation safety

Nuclear Regulatory Authority Act, 2015 (Act 895)

International Nuclear Information System (INIS)

2015-04-01

An Act to establish a Nuclear Regulatory Authority in Ghana. This Act provides for the regulation and management of activities and practices for the peaceful use of nuclear material or energy, and to provide for the protection of persons and the environment against the harmful effects of radiation; and to ensure the effective implementation of the country’s international obligations and for related matters. This Act replaced the Radiation Protection Instrument, of 1993 (LI 1559).

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

International Nuclear Information System (INIS)

Osabe, Takeshi

2014-01-01

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

International conference on strengthening of nuclear safety in Eastern Europe. Armenian Nuclear Regulatory Authority

International Nuclear Information System (INIS)

Nersesyan, V.

1999-01-01

The status of the Armenian Nuclear Regulatory Authority (ANRA) are described in detail with its main task and responsibilities concerning regulations and surveillance of nuclear and radiation safety. The following issues are presented: nuclear legislation; inspection activities; licensing of significant safety related modifications and modernization of NPPs; incidents at NPPs; personnel training; emergency planning; surveillance of nuclear materials; radioactive waste management; and plan of the ANRA perspective development

Professional Nuclear Materials Management

International Nuclear Information System (INIS)

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

1966-01-01

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

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

International Nuclear Information System (INIS)

2011-01-01

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

Developments related to the National Nuclear Safety Authority of Romania

International Nuclear Information System (INIS)

Baciu, Florin

1998-01-01

The contribution presents the status of the National Commission for Nuclear Activity Control (CNCAN) as indicated by the provisions of a Romanian Government Decision of May 1998. As specified in the art.3 the main tasks of the Commission are the following: to issue authorization and exercise permits of activities in nuclear field; to supervise the applications of the provisions stipulated by the law concerning development in safety conditions of nuclear activities; to develop instructions as well as nuclear safety regulations to ensure the quality assurance and functioning in safety conditions of the nuclear facilities and plants, the protection against nuclear radiation of the professionally exposed personnel, of the population, of the environment and of the material goods, the physical protection, the records, preservation and transport of radioactive material and of fissionable materials as well as the management of radioactive waste; organizes expert and is responsible for the state control concerning the integrated application of the law provisions in the field of quality constructions in which nuclear installations of national interest are located, during all the phases and for all the components of the quality system in this field; issues specialty and information documentation specific to its own activity, provides the information of the public through official publication, official statements to the press and other specific form of information; carries out any other tasks provided by law in the field of regulations and control of nuclear activity. Author presents also the CNCAN staff number evolution, the new structure, the staff distribution at headquarters, local agencies and national radiation monitoring network. Finally, the author discusses the legal provisions related to management manual procedures

Inventory of nuclear materials in case of emergency

International Nuclear Information System (INIS)

Portugal, J.L.; Zanetti, S.

2001-01-01

The crisis situations for nuclear materials in nuclear facilities are provided for in the French regulation, as the decree of 12 May 1981 specifies that 'In any circumstance, the Ministry of Industry can order a physical inventory of the materials and its comparison with the accountancy records'. Such an inventory can be ordered in facilities holding category I nuclear materials, in case of a theft for example. The operators must be able to establish quickly if the stolen materials come from their facility. To test the organization set at the operators and competent authority levels respectively, five exercises of increasing complexity have already been carried out. These exercises have permitted the validation of procedures, composition of the various crisis centers, methodology for such an inventory and use of protected communication means. The authority crisis center includes members of the competent Authority and it's technical support body: staff members of the IPSN. It is in charge of the national managing of the operations, in relation with one or several site crisis centers. The site crisis center is the interface between the authorities and the facility crisis center. The operations of inventory are carried out from the roughest checking to the finest ones. To be efficient during the first hours of the crisis, the authority crisis center must have data bases at the disposal of its experts, containing information about physical protection and accountancy of the nuclear materials detained by the site and the relevant facilities. (authors)

Accounting for and control of nuclear material at the Central Institute of Nuclear Research, Rossendorf

International Nuclear Information System (INIS)

Heidel, S.; Rossbander, W.; Helming, M.

1983-01-01

A survey is given of the system of accounting for and control of nuclear material at the Central Institute for Nuclear Research, Rossendorf. It includes 3 material balance areas. Control is implemented at both the institute and the MBA levels on the basis of concepts which are coordinated with the national control authority of the IAEA. The system applied enables national and international nuclear material control to be carried out effectively and economically at a minimum of interference with operational procedures. (author)

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

International Nuclear Information System (INIS)

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

2011-01-01

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

Physical protection of nuclear material

International Nuclear Information System (INIS)

1975-01-01

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

Graphite materials for nuclear reactors

International Nuclear Information System (INIS)

Oku, Tatsuo

1991-01-01

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

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

Science.gov (United States)

2010-01-01

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

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

International Nuclear Information System (INIS)

1978-01-01

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

Management review of nuclear material control and accounting systems

International Nuclear Information System (INIS)

1975-06-01

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

Nuclear technology and materials science

International Nuclear Information System (INIS)

Olander, D.R.

1992-01-01

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

Report on activities of Nuclear Regulatory Authority of the Slovak Republic and safety of nuclear installations in the Slovak Republic in 2009. Annual report

International Nuclear Information System (INIS)

2010-04-01

A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) in 2009 is presented. These activities are reported under the headings: (1) Foreword; (2) Legislation; (3) Issuance of authorizations, assessment, supervisory activities and enforcement; (4) Nuclear safety of nuclear installations in the Slovak Republic; (5) Safety of other nuclear installations; (6) Management of radioactive waste; (7) Nuclear materials and physical protection of nuclear materials; (8) Emergency planning and preparedness; (9) International activities; (10) Public communication; (11) Nuclear Regulatory Authority of the Slovak Republic; (12) UJD SR organization chart; (13) Abbreviations.

Report on activities of Nuclear Regulatory Authority of the Slovak Republic and safety of nuclear installations in the Slovak Republic in 2008. Annual report

International Nuclear Information System (INIS)

Zemanova, D.; Pirozekova, M.

2009-04-01

A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) in 2008 is presented. These activities are reported under the headings: (1) Foreword; (2) Legislation; (3) Issuance of authorizations, assessment, supervisory activities and enforcement; (4) Nuclear safety of nuclear installations in the Slovak Republic; (5) Safety of other nuclear installations; (6) Management of radioactive waste; (7) Nuclear materials and physical protection of nuclear materials; (8) Activity of Building Office; (9) Emergency planning and preparedness; (10) International activities; (11) Public communication; (11) Nuclear Regulatory Authority of the Slovak Republic; (12) UJD SR organization chart; (13) Abbreviations

Safeguards on nuclear materials

International Nuclear Information System (INIS)

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

2001-01-01

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

Nuclear materials transport worldwide

International Nuclear Information System (INIS)

Stellpflug, J.

1987-01-01

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

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)

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

International Nuclear Information System (INIS)

Mencarini, Leonardo de H.; Caldeira, Alexandre D.

2011-01-01

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)

The Report on Activities of the Nuclear Regulatory Authority of the Slovak Republic and on Safety of Nuclear Installations in the Slovak Republic in 2011

International Nuclear Information System (INIS)

2012-05-01

A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) in 2011 is presented. These activities are reported under the headings: Foreword; (1) Legislative activities; (2) Regulatory Activities; (3) Nuclear safety of nuclear power plants; (4) Nuclear Materials in SR; (5) Nuclear materials and physical protection of nuclear materials; (6) Scope of powers of the office building; (7) Emergency planning and preparedness; (8) International activities; (9) Public communication; (10) Nuclear Regulatory Authority of the Slovak Republic; (11) UJD SR organization chart; The International Nuclear Event Scale (INES); (12) Abbreviations.

Structural materials for innovative nuclear systems (SMINS)

International Nuclear Information System (INIS)

2008-01-01

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

The Report on Activities of the Nuclear Regulatory Authority of the Slovak Republic and on Safety of Nuclear Installations in the Slovak Republic in 2010

International Nuclear Information System (INIS)

2010-05-01

A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) in 2010 is presented. These activities are reported under the headings: Address of the Chairperson; (1) Legislative activities; (2) Issuance of authorizations, assessment, supervisory activities and enforcement; (3) Nuclear safety of nuclear power plants; (4) Nuclear materials and physical protection of nuclear materials; (5) Powers of the office building; (6) Emergency planning and preparedness; (7) International activities; (8) Public communication; (9) Nuclear Regulatory Authority of the Slovak Republic; (10) Appendix: UJD SR organization chart; The International Nuclear Event Scale (INES); Abbreviations.

The French nuclear safety authority's experience with radioactive transport inspection

International Nuclear Information System (INIS)

Jacob, E.; Aguilar, J.

2004-01-01

About 300,000 radioactive material packages are transported annually in France. Most consist of radioisotopes for medical, pharmaceutical or industrial use. On the other hand, the nuclear industry deals with the transport of fuel cycle materials (uranium, fuel assemblies, etc.) and waste from power plants, reprocessing plants and research centers. France is also a transit country for shipments such as spent fuel packages from Switzerland or Germany, which are bound for Sellafield in Great Britain. The French nuclear safety authority (DGSNR: Directorate General for Nuclear Safety and Radioprotection) has been responsible since 1997 for the safety of radioactive material transport. This paper presents DGNSR's experience with transport inspection: a feedback of key points based on 300 inspections achieved during the past five years is given

German Democratic Republic State system of accounting for and control of nuclear material

International Nuclear Information System (INIS)

Roehnsch, W.; Gegusch, M.

1976-01-01

The system of accountancy for and control of nuclear material in the German Democratic Republic (GDR) with its legal bases and components is embedded in the overall State system of protection in the peaceful uses of nuclear energy. As the competent State authority, the Nuclear Safety and Radiation Protection Board of the GDR is also responsible for meeting the GDR's national and international tasks in the control of nuclear material. At enterprise level, the observance of all safety regulations for nuclear material, including the regulations for the control, is within the responsibility of managers of establishments, which are in any way concerned with the handling of nuclear material. To support managers and to function as internal control authorities, nuclear material officers have been appointed in these establishments. Design information, operating data, physical inventory of nuclear material and the respective enterprise records and reports are subject to State control by the Nuclear Material Inspectorate of the Nuclear Safety and Radiation Protection Board. This Inspectorate keeps the central records on nuclear material, forwards reports and information to, and maintains the necessary contacts with, the IAEA. For the nuclear material in the GDR four material balance areas have been established for control purposes. To rationalize central recording and reporting, electronic data processing is increasingly made use of. In a year-long national and international control of nuclear material, the State control system has stood the test and successfully co-operates with the IAEA. (author)

Nuclear Regulatory Authority of the Slovak Republic. Annual Report 2003

International Nuclear Information System (INIS)

Seliga, M.

2004-04-01

A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic in 2003 is presented. These activities are reported under the headings: (1) Foreword; (2) Legislation; (3) Assessment and inspection of nuclear installations; (4) Safety analyses; (5) Nuclear materials and physical protection of nuclear installations; (6) Radioactive waste; (7) Quality assurance; (8) Personnel qualification and training; (9) Emergency preparedness; (10) International co-operation; (11) Public information; (12) Personnel and economy data; Appendix: Abbreviations; Radiation safety

Nuclear Regulatory Authority of the Slovak Republic. Annual Report 2004

International Nuclear Information System (INIS)

Seliga, M.

2005-04-01

A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic in 2004 is presented. These activities are reported under the headings: (1) Foreword; (2) Legislation; (3) Assessment and inspection of nuclear power plants; (3.1) Assessment and inspection of other nuclear installations; (3.2) Safety analyses; (4) Nuclear materials and physical protection of nuclear installations; (5) Radioactive waste; (6) Quality assurance; (7) Personnel qualification and training; (8) Emergency preparedness; (9) International co-operation; (10) Public information; (11) Personnel and economy data; Appendix: Abbreviations; INES

The establishment of computer system for nuclear material accounting

International Nuclear Information System (INIS)

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

1988-01-01

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

Evaluation of Terminated Nuclear Material Licenses

International Nuclear Information System (INIS)

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

1999-01-01

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

Physical protection of nuclear materials and facilities in CEA

International Nuclear Information System (INIS)

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

2001-01-01

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

Overview moderator material for nuclear reactor components

International Nuclear Information System (INIS)

Mairing Manutu Pongtuluran; Hendra Prihatnadi

2009-01-01

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

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

International Nuclear Information System (INIS)

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

2014-01-01

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

Nuclear Regulatory Authority of the Slovak Republic. Annual Report 2001

International Nuclear Information System (INIS)

Seliga, M.

2002-04-01

A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic in 2001 is presented. These activities are reported under the headings: (1) Foreword; (2) Legislation; (3) Assessment and inspection of nuclear installations; (4) Safety analyses; (5) Nuclear materials and physical protection of nuclear installations; (6) Radioactive waste (RAW); (7) Quality assurance; (8) Personnel qualification and training; (9) Emergency preparedness; (10) International co-operation; (11) Public information; (12) Personnel and economy data; (13) Conclusion; (14) Appendix: Abbreviations; Radiation safety

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

International Nuclear Information System (INIS)

Gan Lin

2002-01-01

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

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.

Nuclear Regulatory Authority of the Slovak Republic. Annual Report 2002

International Nuclear Information System (INIS)

Seliga, M.

2003-04-01

A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic in 2002 is presented. These activities are reported under the headings: (1) Foreword; (2) Legislation; (3) Assessment and inspection of nuclear installations; (4) Safety analyses; (5) Nuclear materials and physical protection of nuclear installations; (6) Radioactive waste; (7) Quality assurance; (8) Personnel qualification and training; (9) Emergency preparedness; (10) International co-operation; (11) Public information; (12) Personnel and economy data; Appendix: Abbreviations; Special Enclosure: 10. Years of the Nuclear Regulation Authority of the Slovak Republic. An independent and professional state regulatory authority supervising the nuclear safety is one of prerequisites of the safe operation of nuclear installations in each country. In the Slovak Republic this role has been fulfilled by the Nuclear Regulatory Authority (UJD) since 1993. The main mission of UJD set down by the law is to guarantee for the Slovak citizens as well as for international society that the nuclear power on the territory of the Slovak Republic will be used exclusively for peaceful purposes and that the Slovak nuclear installations are designed, constructed, operated and decommissioned in compliance with relevant legal documents. The mission of UJD is also to tender the operation of nuclear installations so that their operation would not jeopardise the nuclear power plant staff or public and would not cause detrimental effects to the environment or property. UJD prepares laws or comments to the laws and issues decrees in the area of its competencies, issues authorisations for operators of nuclear facilities, reviews and evaluates the safety documentation of nuclear installations, performs the inspections at nuclear installations comparing whether the legal requirements are fulfilled and whether the real status of nuclear installations and their operation is or not in compliance with

Gamma spectrometric discrimination of special nuclear materials

International Nuclear Information System (INIS)

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

2012-12-01

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

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)

Nuclear material accounting handbook

International Nuclear Information System (INIS)

2008-01-01

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

Education and training in nuclear materials

International Nuclear Information System (INIS)

Falcon, S.; Marco, M.

2014-01-01

CIEMAT participates in the European project Matisse (Materials Innovations for a Safe and Sustainable nuclear in Europe) belonging to FP7, whose main objective is to promote the link between the respective national research programs through networking and integration of activities for innovation in materials for advanced nuclear systems, sharing among partners best practices and implementation of training tools and efficient communication. The draft four years, from 2013 to 2017, includes aspects such as the interaction between infrastructure, R and D programs and postgraduate education and training. (Author)

Non destructive assay techniques applied to nuclear materials

International Nuclear Information System (INIS)

Gavron, A.

2001-01-01

Nondestructive assay is a suite of techniques that has matured and become precise, easily implementable, and remotely usable. These techniques provide elaborate safeguards of nuclear material by providing the necessary information for materials accounting. NDA techniques are ubiquitous, reliable, essentially tamper proof, and simple to use. They make the world a safer place to live in, and they make nuclear energy viable. (author)

Physical protection of export/import and transportation of nuclear material in the Slovak Republic

International Nuclear Information System (INIS)

Vaclav, J

2002-01-01

Full text: The paper contains short overview about average amount of nuclear materials transported on the territory of the Slovak Republic in a year, and the physical protection of these nuclear materials. There are several types of transportation and export/import of nuclear materials in the SR: fresh fuel import; import of other unirradiated nuclear materials (e.g. depleted uranium, natural uranium); export of unirradiated nuclear materials (e.g. natural uranium); internal transportation of fresh fuel; internal transportation of other unirradiated nuclear materials; internal transportation of spent fuel. The main objective of the nuclear regulatory authority SR is to supervise observation of the national legislation as follows: the act no. 130 / 1998 on peaceful use of nuclear energy; UJD SR's regulation no. 186/1999 which details the physical protection of the nuclear facilities, nuclear materials, and radioactive waste (following requirements of INFCIRC 225 / Rev. 4); UJD SR's regulation no. 284 / 1999 which details conditions of nuclear material and radioactive wastes transportation. (author)

The Report on Activities of the Nuclear Regulatory Authority of the Slovak Republic. Annual Report 2012

International Nuclear Information System (INIS)

2013-04-01

A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) in 2012 is presented. These activities are reported under the headings: Foreword; (1) Legislative activities; (2) Regulatory Activities; (3) Nuclear safety of nuclear power plants; (4) Stress tests on the nuclear power plants; (5) Nuclear Materials in SR; (6) Building Authority; (7) Emergency planning and preparedness; (8) International activities; (9) Public communication; (10) Nuclear Regulatory Authority of the Slovak Republic; (11) Attachments; (12) Abbreviations used.

Topical understandings of nuclear material measurement · accountancy and quality assurance

International Nuclear Information System (INIS)

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

2002-01-01

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

New materials options for nuclear systems

International Nuclear Information System (INIS)

Jones, R.H.; Garner, F.A.; Bruemmer, S.M.; Gelles, D.S.

1989-01-01

Development of new materials for nuclear reactor systems is continuing to produce options for improved reactor designs. Materials with reduced environment-induced crack growth is a key materials issue for the light water reactor (LWR) industry while the development of low activation ferritic, austenitic and vanadium alloys has been an active area for materials development for fusion reactor structural applications. Development of advanced materials such as metal matrix and ceramic matrix composites for reactor systems have received a limited amount of attention. (author)

Competent authority regulatory control of the transport of radioactive material

International Nuclear Information System (INIS)

1987-04-01

The purpose of this guide is to assist competent authorities in regulating the transport of radioactive materials and to assist users of transport regulations in their interactions with competent authorities. The guide should assist specifically those countries which are establishing their regulatory framework and further assist countries with established procedures to harmonize their application and implementation of the IAEA Regulations. This guide specifically covers various aspects of the competent authority implementation of the IAEA Regulations for the Safe Transport of Radioactive Material. In addition, physical protection and safeguards control of the transport of nuclear materials as well as third party liability aspects are briefly discussed. This is because they have to be taken into account in overall transport regulatory activities, especially when establishing the regulatory framework

In-field analysis and assessment of nuclear material

International Nuclear Information System (INIS)

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

1996-01-01

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

LECI Department of Nuclear Materials

International Nuclear Information System (INIS)

2006-01-01

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

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

International Nuclear Information System (INIS)

2007-01-01

exposure and the means of protection against such exposure. Also discussed are the authorized uses of nuclear and other radioactive material and the regime governing their transport. Sections 9-11 offer guidance on how to manage efforts aimed at preventing, detecting and responding to the threat of criminal or unauthorized acts. Appendix I provides statistics on specific cases of illicit trafficking and highlights aspects of these incidents. Appendix II suggests general search procedures for use by responders when the presence of nuclear or other radioactive material is suspected

Control of Nuclear Material in Republic of Croatia

International Nuclear Information System (INIS)

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

2008-01-01

keeping the records concerning nuclear material, the method in which the nuclear material user notifies the state administration body responsible for nuclear safety affairs, as well as the method in which the state administration body responsible for nuclear safety affairs keeps the nuclear materials register and the register of special equipment.(author)

Report on activities of Nuclear Regulatory Authority of the Slovak Republic and safety of nuclear installations in the Slovak Republic in 2007. Annual report

International Nuclear Information System (INIS)

2007-04-01

A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) in 2007 is presented. These activities are reported under the headings: (1) Foreword; (2) Legislation; (3) Issuance of authorizations, assessment, supervisory activities and enforcement; (4) Nuclear safety of nuclear installations in the Slovak Republic; (5) Safety of other nuclear installations; (6) Management of radioactive waste; (7) Nuclear materials; (8) Emergency planning and preparedness; (9) International activities; (10) Public communication; (11) Nuclear Regulatory Authority of the Slovak Republic; (12) Abbreviations

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.

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

International Nuclear Information System (INIS)

Kuk, I. H.; Lee, H. S.; Jeong, Y. H.; Sung, K. W.; Han, J. H.; Lee, J. T.; Lee, H. K.; Kim, S. J.; Kang, H. S.; An, D. H.; Kim, K. R.; Park, S. D.; Han, C. H.; Jung, M. K.; Oh, Y. J.; Kim, K. H.; Kim, S. H.; Back, J. H.; Kim, C. H.; Lim, K. S.; Kim, Y. Y.; Na, J. W.; Ku, J. H.; Lee, D. H.

1996-12-01

A study on the nuclear materials technologies which are necessary to establish the base for alloy development was performed. - The feasibility study on the application of Zircaloy scrap waste for hydrogen storage - The development of metal hydride battery for energy storage system - The establishment of transmission electron microscopy database for nuclear materials - The basic technology for the development of cladding materials for high burnup - The water chemistry technology for secondary system pH control and the photocatalysis technology for decomposition and removal of organics. - Improvement of primary component integrity of PWR by Zinc injection. (author). 175 refs., 58 tabs., 262 figs

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

International Nuclear Information System (INIS)

Burmester, M.; Helming, M.

1984-01-01

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

International nuclear material safeguards

International Nuclear Information System (INIS)

Syed Azmi Syed Ali

1985-01-01

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

Study of nuclear environment and material strategy

International Nuclear Information System (INIS)

Kamei, Takashi

2011-01-01

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

Fourth Collaborative Materials Exercise of the Nuclear Forensics International Technical Working Group

International Nuclear Information System (INIS)

Schwantes, J.M.; Reilly, D.; Marsden, O.

2018-01-01

The Nuclear Forensics International Technical Working Group is a community of nuclear forensic practitioners who respond to incidents involving nuclear and other radioactive material out of regulatory control. The Group is dedicated to advancing nuclear forensic science in part through periodic participation in materials exercises. The Group completed its fourth Collaborative Materials Exercise in 2015 in which laboratories from 15 countries and one multinational organization analyzed three samples of special nuclear material in support of a mock nuclear forensic investigation. This special section of the Journal for Radioanalytical and Nuclear Chemistry is devoted to summarizing highlights from this exercise. (author)

Nuclear material accounting software for Ukraine

International Nuclear Information System (INIS)

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

1999-01-01

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

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

International Nuclear Information System (INIS)

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

1988-01-01

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

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

International Nuclear Information System (INIS)

Hong, Jun Hwa; Ryu, Woo Seog; Chi, Se Hwan; Lee, Bong Sang; Oh, Yong Jun; Byun, Thak Sang; Oh, Jong Myung

1994-07-01

This report reviews the status of R and D and the material specifications of nuclear components in order to develop the stainless steels for nuclear applications, and the technology of computer-assisted alloy design is developed to establish the thermodynamic data of Fe-Cr-Ni-Mo-Si-C-N system which is the basic stainless steel systems. High strength and corrosion resistant stainless steels, 316LN and super clean 347, are developed, and the manufacturing processes and heat treatment conditions are determined. In addition, a martensitic steel is produced as a model alloy for turbine blade, and characterized. The material properties showed a good performance for nuclear applications. (Author)

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

International Nuclear Information System (INIS)

Charpentier, Th.

2007-10-01

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

The role of national regulatory authority in monitoring of radioactivity and in case of seizure of radioactive or nuclear material

International Nuclear Information System (INIS)

Morkunas, G.

2002-01-01

Full text: The Radiation Protection Centre is a regulatory authority in radiation protection in Lithuania. Its main tasks are licensing of practices, supervision, control and enforcement of radiation protection requirements, dosimetric, radiometric and spectrometric measurements, evaluation of exposure and its sources, expertise and advice on optimization of radiation protection. Its activities may be divided into two main parts -- regulatory and analytical ones. Food, drinking water, environmental, wipe and other samples are monitored, the appropriate evaluation of doses is done. The data on concentrations of artificial radionuclides in different bodies are available. The laboratory is to be accredited according to the ISO 17025 standard in the framework of Phare Twinning Project. In case of seized radioactive or nuclear material the Radiation Protection Centre has to identify the necessary radiation protection means for members of public and emergency workers, perform measurements of dose rate and radioactive contamination, and, if necessary, evaluate doses received due to the seized radioactive or nuclear material. Since the Radiation Protection Centre has its departments in the largest cities of Lithuania the above mentioned measures can be taken very urgently, especially the ones connected with primary evaluation of situation and identification of optimized radiation protection measures. The Radiation Protection Centre has its own possibilities of identification of radionuclides in the seized material. Such installations as HpGe spectrometers (Oxford and Canberra), equipment for radiochemical separation of U, Pu and actinides, alpha spectrometer, liquid scintillation spectrometer and neutron rem counter are available. There were a few cases when seized material had to be analyzed also. Different sources were found in different places of Lithuania, and it was necessary to define the activity and isotopic content of these sources. The following scheme is used in

Software development for managing nuclear material database

International Nuclear Information System (INIS)

Tondin, Julio Benedito Marin

2011-01-01

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

The system of nuclear material control of Kazakhstan

International Nuclear Information System (INIS)

Yeligbayeva, G.Zh.

2001-01-01

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

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

Science.gov (United States)

2010-01-01

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

Materials for nuclear reactors

International Nuclear Information System (INIS)

Banerjee, S.; Kamath, H.S.

2005-01-01

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

An accountancy system for nuclear materials control in research centres

International Nuclear Information System (INIS)

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

1979-01-01

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

Radiation damage studies of nuclear structural materials

International Nuclear Information System (INIS)

Barat, P.

2012-01-01

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

Structural integrity of materials in nuclear service: a bibliography

International Nuclear Information System (INIS)

Heddleson, F.A.

1977-01-01

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

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.

Bulk material management mode of general contractors in nuclear power project

International Nuclear Information System (INIS)

Zhang Jinyong; Zhao Xiaobo

2011-01-01

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

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

International Nuclear Information System (INIS)

2018-01-01

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

Radiation damage in nuclear waste materials

International Nuclear Information System (INIS)

Jencic, I.

2000-01-01

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

New challenges in nuclear material detection

International Nuclear Information System (INIS)

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

2002-01-01

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

Software for MUF evaluating in item nuclear material accounting

International Nuclear Information System (INIS)

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

2009-01-01

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

Selection of materials in nuclear fuel: present and future

International Nuclear Information System (INIS)

Munoz-Reja, C.; Fuentes, L.; Garcia de la Infanta, J. M.; Munoz Sicilia, A.

2013-01-01

One of the main aspects of the nuclear fuel is the selection of materials for the components. The operating conditions of the fuel elements impose a major challenge to materials: high temperature, corrosive aqueous environment, high mechanical properties, long periods of time under these extreme conditions and what is the differentiating factor; the effect of irradiation. The materials are selected to fulfill these severe requirements and also to be able to control and to predict its behavior in the working conditions. Their development, in terms of composition and processing, is based on the continuous follow-up of the operation behavior. Many of these materials are specific of the nuclear industry, such as the uranium dioxide and the zirconium alloys. This article presents the selection and development of the nuclear fuel materials as a function of the services requirements. It also includes a view of the new nuclear fuels materials that are being raised after Fukushima accident. (Author)

The French Nuclear Safety Authority (ASN)

International Nuclear Information System (INIS)

Alloso, Ph.

2011-01-01

This article presents the statutes, the organization and the missions of the Nuclear Safety Authority (ASN) whose scope includes radiation protection since 2002. Globally ASN is in charge of: -) participating to the making of laws and regulations, -) delivering administrative authorizations, -) controlling the conformity of nuclear installations and activities with the laws and regulations, -) informing the public, and -) reporting on the state of nuclear safety and radiation protection each year. (A.C.)

Security of nuclear materials using fusion multi sensor wavelett

International Nuclear Information System (INIS)

Djoko Hari Nugroho

2010-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Fujita, Mitsutane; Noda, Tetsuji [National Research Institute for Metals, Tsukuba, Ibaraki (Japan)

2001-03-01

A database for transmutation and radioactivity of nuclear materials is required for selection and design of materials used in various nuclear reactors. The database based on the FENDL/A-2.0 on the Internet and the additional data collected from several references has been developed in NRIM site of 'Data-Free-Way' on the Internet. Recently, the function predicted self-shielding effect of materials for {gamma}-ray was added to this database. The user interface for this database has been constructed for retrieval of necessary data and for graphical presentation of the relation between the energy spectrum of neutron and neutron capture cross section. It is demonstrated that the possibility of chemical compositional change and radioactivity in a material caused by nuclear reactions can be easily retrieved using a browser such as Netscape or Explorer. (author)

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

International Nuclear Information System (INIS)

Fujita, Mitsutane; Noda, Tetsuji

2001-01-01

A database for transmutation and radioactivity of nuclear materials is required for selection and design of materials used in various nuclear reactors. The database based on the FENDL/A-2.0 on the Internet and the additional data collected from several references has been developed in NRIM site of 'Data-Free-Way' on the Internet. Recently, the function predicted self-shielding effect of materials for γ-ray was added to this database. The user interface for this database has been constructed for retrieval of necessary data and for graphical presentation of the relation between the energy spectrum of neutron and neutron capture cross section. It is demonstrated that the possibility of chemical compositional change and radioactivity in a material caused by nuclear reactions can be easily retrieved using a browser such as Netscape or Explorer. (author)

Safeguards for special nuclear materials

International Nuclear Information System (INIS)

Carlson, R.L.

1979-12-01

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

Dealing with the regional challenge of physical protection of nuclear materials

International Nuclear Information System (INIS)

Paschoa, A.S.

2002-01-01

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

Application of artificial neural network to identify nuclear materials

International Nuclear Information System (INIS)

Xu Peng; Wang Zhe; Li Tiantuo

2005-01-01

Applying the neutral network, the article studied the technology of identifying the gamma spectra of the nuclear material in the nuclear components. In the article, theory of the network identifying the spectra is described, and the results of identification of gamma spectra are given.(authors)

Nuclear data information system for nuclear materials

International Nuclear Information System (INIS)

Fujita, Mitsutane; Noda, Tetsuji; Utsumi, Misako

1996-01-01

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

Nuclear security recommendations on nuclear and other radioactive material out of regulatory control: Recommendations

International Nuclear Information System (INIS)

2011-01-01

The purpose of this publication is to provide guidance to States in strengthening their nuclear security regimes, and thereby contributing to an effective global nuclear security framework, by providing: - Recommendations to States and their competent authorities on the establishment or improvement of the capabilities of their nuclear security regimes, for carrying out effective strategies to deter, detect and respond to a criminal act, or an unauthorized act, with nuclear security implications, involving nuclear or other radioactive material that is out of regulatory control; - Recommendations to States in support of international cooperation aimed at ensuring that any nuclear or other radioactive material that is out of regulatory control, whether originating from within the State or from outside that State, is placed under regulatory control and the alleged offenders are, as appropriate, prosecuted or extradited

Methodologies for nuclear material accounting and control: challenges and expectations

International Nuclear Information System (INIS)

Ramakumar, K.L.

2007-01-01

Nuclear Material Accounting and Control (NUMAC) represents one of the most important and indispensable responsibilities of any nuclear installation. The emphasis is to ensure that the nuclear material being handled in the nuclear installation is properly accounted for with the expected accuracy and confidence levels. A number of analytical methods based on both destructive and non-destructive assay techniques are available at the disposal of the nuclear analytical scientists for this purpose and they have been enumerated extensively in literature. Instead of recounting the analytical methodologies available, an attempt has been made in this paper to highlight some of the challenges. (author)

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

International Nuclear Information System (INIS)

1979-01-01

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

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

International Nuclear Information System (INIS)

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

2001-01-01

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

Nuclear and hazardous material perspective

International Nuclear Information System (INIS)

Sandquist, Gary M.; Kunze, Jay F.; Rogers, Vern C.

2007-01-01

The reemerging nuclear enterprise in the 21. century empowering the power industry and nuclear technology is still viewed with fear and concern by many of the public and many political leaders. Nuclear phobia is also exhibited by many nuclear professionals. The fears and concerns of these groups are complex and varied, but focus primarily on (1) management and disposal of radioactive waste [especially spent nuclear fuel and low level radioactive waste], (2) radiation exposures at any level, and (3) the threat nuclear terrorism. The root cause of all these concerns is the exaggerated risk perceived to human health from radiation exposure. These risks from radiation exposure are compounded by the universal threat of nuclear weapons and the disastrous consequences if these weapons or materials become available to terrorists or rogue nations. This paper addresses the bases and rationality for these fears and considers methods and options for mitigating these fears. Scientific evidence and actual data are provided. Radiation risks are compared to similar risks from common chemicals and familiar human activities that are routinely accepted. (authors)

Transportation of nuclear material in France: regulatory and technical aspects

International Nuclear Information System (INIS)

Flory, D.; Renard, C.

1995-01-01

Legislative and regulatory documentation define responsibilities in the field of security and physical protection for transportation of nuclear material. Any transportation activity has to conform to an advance authorization regime delivered by the Ministry of Industry. Responsibility for physical protection of nuclear material rests with the carrier under control of the public authority. Penalties reinforce this administrative regime. Operational responsibility for management and control of transport operations has been entrusted by the ministry to the operational transport unit (Echelon Operationnel des Transports - EOT) of IPSN (Institute for Nuclear Protection and Safety). To guarantee en efficient protection of transport operations, the various following means are provided for: -specialized transport means; - devices for real time tracking of road vehicles; - administrative authorization and declaration procedures; -intervention capacities in case of sabotage... This set of technical means and administrative measures is completed by the existence of a body of inspectors who may control every step of the operations. (authors). 3 tabs

Croatian National System of Nuclear Materials Control

International Nuclear Information System (INIS)

Biscan, R.

1998-01-01

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

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

International Nuclear Information System (INIS)

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

2000-01-01

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

Sample size optimization in nuclear material control. 1

International Nuclear Information System (INIS)

Gladitz, J.

1982-01-01

Equations have been derived and exemplified which allow the determination of the minimum variables sample size for given false alarm and detection probabilities of nuclear material losses and diversions, respectively. (author)

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

International Nuclear Information System (INIS)

1981-01-01

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

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

International Nuclear Information System (INIS)

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

1993-01-01

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

Raising awareness about protection and control of nuclear materials held by 'small-scale holders'

International Nuclear Information System (INIS)

Ladsous, D.; Coulie, E.; Giorgio, M.

2013-01-01

In France, the activities carried out by the 'small-scale holders' of nuclear materials are organized by a specific regulatory system which defines in a detailed way their obligations and the means of control of the government. The first part of the article presents the legal framework relating to the use of nuclear materials by small-scale holders in civilian fields. The importance of the declaration of the nuclear material inventory is clearly emphasized and must be prepared and transmitted to the Institute for Radiological Protection and Nuclear Safety (IRSN) every year. The second part describes how this declaration is used to provide basic information for the competent Ministry and the inspectors to check the correct application of the regulatory requirements relating to physical protection and to the control of nuclear materials. Finally, the last part presents the on-site inspections carried out by sworn and accredited inspectors under the authority of the competent Authority, which provide an overall picture and allow an evaluation of the risks of theft, loss or diversion of these materials. (authors)

Subcritical calculation of the nuclear material warehouse

International Nuclear Information System (INIS)

Garcia M, T.; Mazon R, R.

2009-01-01

In this work the subcritical calculation of the nuclear material warehouse of the Reactor TRIGA Mark III labyrinth in the Mexico Nuclear Center is presented. During the adaptation of the nuclear warehouse (vault I), the fuel was temporarily changed to the warehouse (vault II) and it was also carried out the subcritical calculation for this temporary arrangement. The code used for the calculation of the effective multiplication factor, it was the Monte Carlo N-Particle Extended code known as MCNPX, developed by the National Laboratory of Los Alamos, for the particles transport. (Author)

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

Science.gov (United States)

2010-01-01

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

Calcium phosphate nuclear materials: apatitic ceramics for separated wastes

International Nuclear Information System (INIS)

Carpena, J.; Lacout, J.L.

2005-01-01

Is it feasible to elaborate conditioning materials for separated high activity nuclear wastes, as actinides or fission products? Specific materials have been elaborated so that the waste is incorporated within the crystalline structure of the most stable calcium phosphate, i.e. apatite. This mineral is able to sustain high irradiation doses assuming a well chosen chemical composition. Mainly two different ways of synthesis have been developed to produce hard apatite ceramics that can be used to condition nuclear wastes. Here we present a data synthesis regarding the elaboration of these apatite nuclear materials that includes experiments on crystallo-chemistry, chemical analysis, leaching and irradiation tests performed for the past fifteen years. (authors)

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

International Nuclear Information System (INIS)

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

2012-01-01

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

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)

Software development for managing nuclear material database; Desenvolvimento de um programa computacional para gerenciamento de banco de dados de material nuclear

Energy Technology Data Exchange (ETDEWEB)

Tondin, Julio Benedito Marin

2011-07-01

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

Nuclear reactors: physics and materials

Energy Technology Data Exchange (ETDEWEB)

Yadigaroglu, G

2005-07-01

In the form of a tutorial addressed to non-specialists, the article provides an introduction to nuclear reactor technology and more specifically to Light Water Reactors (LWR); it also shows where materials and chemistry problems are encountered in reactor technology. The basics of reactor physics are reviewed, as well as the various strategies in reactor design and the corresponding choices of materials (fuel, coolant, structural materials, etc.). A brief description of the various types of commercial power reactors follows. The design of LWRs is discussed in greater detail; the properties of light water as coolant and moderator are put in perspective. The physicochemical and metallurgical properties of the materials impose thermal limits that determine the performance and the maximum power a reactor can deliver. (author)

The changing role of nuclear materials accounting

International Nuclear Information System (INIS)

Gibbs, P.W.

1995-01-01

Nuclear materials accounting and accounting systems at what have been DOE Production sites are evolving into management decision support tools. As the sites are moving into the mode of making decisions on how to disposition complex and varied nuclear material holdings, the need for complete and many times different information has never been greater. The artificial boundaries that have historically been established between what belongs in the classic material control and accountability (MC and A) records versus what goes into the financial, radiological control, waste, or decommissioning and decontamination records are being challenged. In addition, the tools historically used to put material into different categories such as scrap codes, composition codes, etc. have been found to be inadequate for the information needs of today. In order to be cost effective and even, more importantly to effectively manage -our inventories, the new information systems the authors design have to have the flexibility to serve many needs. In addition, those tasked with the responsibility of managing the inventories must also expand beyond the same artificial boundaries. This paper addresses some of the things occurring at the Savannah River Site to support the changing role of nuclear materials accounting

Measures for prevention illicit trafficking of nuclear and radioactive materials

International Nuclear Information System (INIS)

Strezov, A.

2002-01-01

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

Auditing nuclear materials statements

International Nuclear Information System (INIS)

Anon.

1973-01-01

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

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

International Nuclear Information System (INIS)

Kawasaki, Masashi; Kageyama, Tomio; Suzuki, Toru

2004-01-01

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

The nuclear materials contraband

International Nuclear Information System (INIS)

Williams, P.; Woessner, P.

1996-01-01

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

'Low-activation' fusion materials development and related nuclear data needs

International Nuclear Information System (INIS)

Cierjacks, S.

1990-01-01

So-called ''low-activation'' materials are presently considered as an important means of improving the safety characteristics of future DT fusion reactors. Essential benefits are expected in various problem areas ranging from operation considerations to aspects of decommissioning and waste disposal. Present programs on ''low-activation'' materials development depend strongly on reliable activity calculations for a wide range of technologically important materials. The related nuclear data requirements and important needs for more and improved nuclear data are discussed. (author). 32 refs, 4 figs, 4 tabs

Better materials for nuclear energy

International Nuclear Information System (INIS)

Banerjee, S.

2005-01-01

material joining are some outstanding issues, which need to be addressed for the successful development of high temperature reactor systems. The presentation will conclude by listing various materials related phenomena, which have a strong bearing on the successful development of future nuclear energy systems. (author)

Risk classification for nuclear facilities in connection with the illegal use of nuclear materials

International Nuclear Information System (INIS)

Bahm, W.; Naegele, G.; Sellinschegg, D.

1976-01-01

It is shown, and illustrated by an example, that specific conditions at a nuclear facility to a large extent determine the probability of a successful illegal attack against that facility. Therefore, a categorization of nuclear materials according to the associated hazards alone, as practised currently, does not appear to be sufficient for the establishment of a balanced national physical protection system. In this paper a possible way of categorizing nuclear facilities according to the associated risks, determined as objectively as possible, is discussed. It is felt that initially the analysis should be restricted to the determination of the conditional risks, associated with illegal acquisition and use of radioactive materials by a postulated hostile or similar group. (author)

Domestic round robin exercise on analysis of uranium for nuclear material handling facilities in Japan

International Nuclear Information System (INIS)

Kato, Yoshiyasu; Nagai, Kohta; Handa, Takamitsu; Inoue, Shin-ichi; Sato, Yoshihiro

2016-01-01

Interlaboratory comparison programme as well as internal quality control system is an effective tool for an analytical laboratory responsible to nuclear material accountancy of a nuclear facility to maintain and enhance its capability for analysis. However, it is a burden on nuclear material handling facilities in Japan to attend interlaboratory comparison programme run by overseas institutions because of high costs and complicated procedure for importing nuclear materials, and therefore facilities which can participate in such international programme would be limited. Nuclear Material Control Center has hence started and organised an annual domestic round robin exercise on analysis of uranium standard materials, funded by the Japan Safeguards Office of the Nuclear Regulation Authority, since 2008 to enhance analytical capability of Japanese Facilities. The outline of the round robin exercise will be given and the results of uranium isotopic and concentration analysis reported by participant facilities from 2008 to 2015 will be summarised in the presentation. (author)

Physics and technology of nuclear materials

International Nuclear Information System (INIS)

Ursu, I.

1985-01-01

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

Interatomic potentials for materials of nuclear interest

International Nuclear Information System (INIS)

Fernandez, Julian R.; Monti, Ana M.; Pasianot, Roberto C.; Simonelli, G.

2007-01-01

Procedures to develop embedded atom method (EAM) interatomic potentials are described, with foreseeable applications in nuclear materials. Their reliability is shown by evaluating relevant properties. The studied materials are Nb, Zr and U. The first two were then used to develop an inter species potential for the Zr-Nb binary system. In this sense, the Fe-Cu system was also studied starting from Fe and Cu potentials extracted from the literature. (author) [es

Report on Activities of the Nuclear Regulatory Authority of the Slovak Republic and on Safety of Nuclear Installations in the Slovak Republic in 2006. Annual Report 2006

International Nuclear Information System (INIS)

Zemanova, D.; Pirozekova, M.

2007-04-01

A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic in 2006 is presented. These activities are reported under the headings: Foreword; (1) Vision, Mission and Principles of Activities; (2) Legislation; (3) Issuance of Authorisations, Safety Assessment and Enforcement; (3.1) Issuance of Authorizations/Permissions; (3.2) Assessment and Inspections Activities; (3.3) Safety Assessment and Enforcement; (4) Nuclear Safety of Nuclear Installations in the Slovak Republic; (4.1) Nuclear installations in operation in the Slovak Republic; (4.2) Nuclear Installations under construction in the Slovak Republic; (4.3) Decommissioning of nuclear installations in the Slovak Republic; (5) Safety of Other Nuclear Installations; (5.1) Other Nuclear Installations in Operation; (5.2) Other Nuclear Installations under Construction; (5.3) Other Nuclear Installations under Decommissioning; (6) Management of Radioactive Waste; (6.1) Generation and minimisation of radioactive waste; (6.2) Management of radioactive waste; (6.3) Pre-disposal management of radioactive waste; (6.4) Disposal of radioactive waste; (6.5) Shipment of radioactive waste; (7) Nuclear Materials; (7.1) Accounting for and Control of Nuclear Materials; (7.2) Shipment of Nuclear Materials; (7.3) Illicit Trafficking of Nuclear Materials and Other Radioactive Material; (8) Emergency Planning and Preparedness; (9) International Activities; (9.1) European Affairs; (9.2) Membership in International Organisations; (9.3) Fulfilment of Obligations under International Contractual Instruments; (9.4) Bilateral Co-operation; (10) Public Communication; (11) UJD SR; (11.1) Economy Data; (11.2) Human resources and training; (11.3) Internal Management Quality System; (11.4) Development of UJD SR Regulatory Activities; (12) Abbreviations

Classification of scrap material from nuclear power plants as acceptable for recirculation

International Nuclear Information System (INIS)

Bergman, C.

1983-06-01

The Swedish National Institute of Radiation Protection has in a principal decision accepted that scrap material from nuclear power plants, that contains or may contain radioactive material, can be recirculated. The document is an English translation of the background material for the Board meeting decision and gives some guide-lines for the authority when dealing with this questions. (author)

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

International Nuclear Information System (INIS)

1987-01-01

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

Global nuclear material control model

International Nuclear Information System (INIS)

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

1996-01-01

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

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

International Nuclear Information System (INIS)

Fechner, J.B.

2001-01-01

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

Absolute nuclear material assay

Science.gov (United States)

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

2010-07-13

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

Management of Small Quantity of Nuclear Material at Locations Outside Facilities in Korea

Energy Technology Data Exchange (ETDEWEB)

Park, Seung Sik; Kim, Ki Hyun [KAERI, Daejeon (Korea, Republic of)

2016-05-15

Small quantity of nuclear material (SQNM) is prescribed to be less than specified minimum quantities of nuclear material in a facility. SQNM is used at the locations called locations outside facilities (LOFs). LOFs are used to control the locations and installations that store nuclear materials under one effective Kg, respectively. Holders of SQNM don't need to require a license for use or possession of Uranium or Thorium exclusively for non-nuclear activities, or neither report them to the System of Accounting for and Control of nuclear material (SSAC) under specified quantities according to the Atomic Safety Law. Well defined safeguards law is fundamental to the effective control of nuclear material, facilities and nuclear related activities. In the current nuclear safety legislation, there are some exceptive clauses. Users of SQNM don't need to require a license for use or possession of Uranium or Thorium exclusively for non-nuclear activities, or not report them to the national authority below specified amount.

Management of Small Quantity of Nuclear Material at Locations Outside Facilities in Korea

International Nuclear Information System (INIS)

Park, Seung Sik; Kim, Ki Hyun

2016-01-01

Small quantity of nuclear material (SQNM) is prescribed to be less than specified minimum quantities of nuclear material in a facility. SQNM is used at the locations called locations outside facilities (LOFs). LOFs are used to control the locations and installations that store nuclear materials under one effective Kg, respectively. Holders of SQNM don't need to require a license for use or possession of Uranium or Thorium exclusively for non-nuclear activities, or neither report them to the System of Accounting for and Control of nuclear material (SSAC) under specified quantities according to the Atomic Safety Law. Well defined safeguards law is fundamental to the effective control of nuclear material, facilities and nuclear related activities. In the current nuclear safety legislation, there are some exceptive clauses. Users of SQNM don't need to require a license for use or possession of Uranium or Thorium exclusively for non-nuclear activities, or not report them to the national authority below specified amount

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

International Nuclear Information System (INIS)

Zhang Min; Jue Ji; Liu Tianshu

2013-01-01

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

Status of national system of accounting for and control of nuclear materials in Turkey

International Nuclear Information System (INIS)

Yucel, A.

1999-01-01

Regulating the nuclear activities in Turkey is at the responsibility of Turkish Atomic Energy Authority (TAEA). Under the TAEA Act, the Authority is responsible for national security and protection of the peaceful uses of nuclear energy. After signing the Safeguards Agreement with the IAEA for the application of safeguards in connection with the NPT, a State System of Accounting for and Control of Nuclear Materials (SSAC) has been established. This paper covers national safeguards activities and implementation of SSAC and activities for upgrading of national system. These activities are the part of the IAEA programme on strengthening the effectiveness and improving the efficiency of the safeguards system and on combating illicit trafficking of nuclear materials and other radioactive sources. (author)

Safety of nuclear installations in the Slovak Republic and activities of the Nuclear Regulatory Authority of the Slovak Republic in 2007

International Nuclear Information System (INIS)

Zemanova, D.

2008-01-01

Prepared pursuant to the provisions of the Atomic Act, the report provides information on the safety of nuclear installation in the Slovak Republic and activities of the Nuclear Regulatory Authority of the Slovak Republic ( UJD SR). UJD SR executes its activities in the area of legislation, issuance of authorizations and permissions for the siting, construction, operation and decommissioning of nuclear installations, in the area of reviews, assessments and control of nuclear safety of nuclear installations and emergency planning, in the area of records and accountability of nuclear materials, independent public information and in the area of international co-operation focused on peaceful uses of nuclear power. Based on the results of inspection activities and evaluation of safety indicators, UJD SR assessed the operation of nuclear installations in the Slovak Republic as safe and reliable. No significant event that could have a negative impact on the personnel, population or environment occurred in 2007. (orig.)

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

Securing nuclear warheads and materials: seven steps for immediate action

International Nuclear Information System (INIS)

Bunn, M.

2002-01-01

Full text: In the last decade, substantial progress has been made in improving security and accounting for nuclear weapons and weapons-usable nuclear material worldwide, both by states' own domestic actions and through international cooperation. Thousands of nuclear warheads and hundreds of tons of nuclear material are demonstrably more secure than they were before, and through programs such as the U.S.-Russian Highly Enriched Uranium (He) Purchase Agreement, enough potentially vulnerable bomb material for thousands of nuclear weapons has been verifiably destroyed. Since the attacks of September 11, 2001, the international community has attempted to expand and accelerate these efforts. But much more remains to be done. This paper summarizes a recent report from Harvard University, which recommended seven further steps for immediate action in U.S.-Russian and international cooperation. It covers two recommendations that may be of particular interest to this audience in detail. The first is a proposed program to remove nuclear material entirely from many of the most vulnerable sites around the world (by offering incentives targeted to the needs of each facility to give up the material at that site). The second is a suggestion that participants in the global partnership against the spread of weapons and materials of mass destruction announced at the June 2002 Group of Eight summit make a political commitment to meet stringent security standards for nuclear materials on their territories, and urge (and assist) other states to do likewise. (author)

Towards a new system of accounting of nuclear material

International Nuclear Information System (INIS)

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

1999-01-01

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

Nuclear data needs for material analysis

International Nuclear Information System (INIS)

Molnar, Gabor L.

2001-01-01

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

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

International Nuclear Information System (INIS)

Midiana Ariethia; Muhamad Ilman A A; Mas Pungky Hendrawijaya

2011-01-01

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

NECSA'S Need to Establish a Nuclear Forensics Specific NDA Facility for On-Site Categorization of Seized Nuclear Materials

International Nuclear Information System (INIS)

Boshielo, P.; Mogafe, R.

2015-01-01

The increase of nuclear material that are out of regulatory control is becoming a serious concern and threat and thereby continuously seeking urgent interventions and counteractions from the international community aspiring effective control over all nuclear material and peaceful uses of nuclear technologies globally. In South Africa the nuclear forensics initiative approach and its execution have been adopted, established and managed by the South African Nuclear Energy Corporation (NECSA) to support the country's nuclear safeguards system and nuclear security investigations plan to fight against the illicit trafficking of nuclear and radioactive materials. On this nuclear forensics initiative approach adopted by Necsa, the development and later execution of a Non-Destructive Analyses (NDA) facility capability for quick categorization of any seized nuclear material by law-enforcement agencies is currently envisaged as a critical initiative to comprehend nuclear forensics Laboratory analytical or characterization techniques. The main objective for this NDA facility is planned to be used for performing nuclear material screening process for material categorization purposes to generate information and results which will be open to law enforcement agencies for prosecution processes and also for the safeguards reporting to the IAEA (ITDB). The NDA technique is therefore found to be a critical tool needed at NECSA as an Early-Checking-Point or first-line material check point for all seized nuclear materials in determining some characteristics of the materials and collection of data without having to destroy or changing the morphology of the material. (author)

Nuclear Security Recommendations on Physical Protection of Nuclear Material and Nuclear Facilities (INFCIRC/225/Revision 5). Recommendations (Spanish Edition); Recomendaciones de Seguridad Fisica Nuclear sobre la Proteccion Fisica de los Materiales y las Instalaciones Nucleares (INFCIRC/225/Rev.5). Recomendaciones

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-06-15

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.

Evaluating the Aspect of Nuclear Material in Fuel Cycles

Energy Technology Data Exchange (ETDEWEB)

Takagi, Shunsuke; Pickett, Susan; Oda, Takuji; Choi, Jor-Shan; Kuno, Yusuke; Takana, Satoru [Department of Nuclear Engineering and Management, The University of Tokyo, 7-3-1 Hongo, Bunkyo-ku, Tokyo 113-8685 (Japan); Nagasaki, Shinya [Nuclear Professional School, The University of Tokyo (Japan)

2009-06-15

The increasing number of countries that wish to introduce nuclear power plants raises attention to proliferation resistance in nuclear power plants, and nuclear fuel cycle facilities. In order to achieve adequate proliferation resistance, it is important to evaluate it and to construct effective international institutional frameworks as well as technologies involving high level of proliferation resistance. Although some methods have been proposed for evaluation of the proliferation resistance, their validities have not been investigated in detail. In the present paper, therefore, we compare some of the proposed methodologies. It is essential to detect the abuse or diversion of nuclear material before the nuclear explosive device can be manufactured in order to prevent proliferation. The time needed for the detection of material primary depends on the safeguards that the country applies, and the time needed for fabrication mainly depends on the attributes of the nuclear material. Hence, we divided the proliferation resistance into two parts: the level of safeguards and the material. For examination of evaluation methods such as the one proposed by Charlton [1] or the figure of merit (FOM) [2], sensitivity analysis was performed on weighting factors and scenarios. The validity and characteristics of each method were discussed, focusing on the applicability of each method to the assessment of multi-national approaches such as GNEP. [1] W. S. Charlton, R. L. LeBouf, C. Gariazzo, D. G. Ford, C. Beard, S. Landeberger, M. Whitaker, 'Proliferation resistance assessment methodology for nuclear fuel cycles', Nuclear Technology, 157, 1 (2007). [2] C.G. Bathke et al, 'An assessment of the proliferation resistance of materials in advanced nuclear fuel cycles', 8. International Conference on Facility Operations (2008). (authors)

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

International Nuclear Information System (INIS)

1984-01-01

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

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

International Nuclear Information System (INIS)

Knapp, V.

2002-01-01

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

Materials qualification for nuclear power plants

International Nuclear Information System (INIS)

Braconi, F.

1987-01-01

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)

The criticality check and its applicability for nuclear material accounting

International Nuclear Information System (INIS)

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

1988-01-01

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

Definition of Nuclear Material in Aspects of Nuclear Nonproliferation and Security

International Nuclear Information System (INIS)

Jeon, Ji Hye; Lee, Chan Suh

2014-01-01

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

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

Nuclear material discovery or loss: the French experience

International Nuclear Information System (INIS)

Zanetti, S.H.

2006-01-01

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

Strengthened implementation of physical protection of nuclear material and nuclear facilities in the Republic of Korea

International Nuclear Information System (INIS)

Shim, H.-W.; Lee, J.-U.

2005-01-01

Full text: Since the 9.11 terror, strengthening physical protection has been an accelerated trend internationally. IAEA has been requesting that member states implement a strengthened physical protection of nuclear facilities on the basis of threat assessments. In order to cope with this demand, the Korean government promulgated the 'Law for Physical Protection and Radiological Emergency Preparedness (LPPRE)' as a substantial countermeasure against possible threats. Pursuant to LPPRE, which entered into force on February 16, 2004, nuclear enterprisers are obliged to implement an effective physical protection of nuclear materials, get approval for its physical protection system, and be constantly inspected on. The Ministry of Science and Technology (MOST) approved physical protection regulations of 24 domestic facilities operated by 14 enterprisers. National Nuclear management and Control Agency (NNCA) is entrusted with physical protection related duty and has been conducting physical protection inspection on nuclear materials in use, storage and transport. In addition, NNCA has established the methodology of threat assessment that entails organizing the threat assessment working group to develop a design basis threat (DBT). Korea is putting its best efforts to construct the threat assessment system and strengthen domestic physical protection regime in cooperation with competent authorities. (author)

Nuclear materials management storage study

International Nuclear Information System (INIS)

Becker, G.W. Jr.

1994-02-01

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

Regulation of nuclear materials control and accountability and inspection practices in the Russian Federation

International Nuclear Information System (INIS)

Volodin, Y.G.; Dimitriev, A.M.; Krouptchatnikov, B.N.

1999-01-01

Review and assessment of the resent state orders and directives regulating nuclear materials control and accountability, defining responsibilities and incorporation of different agencies in nuclear materials control and accountability (MC and A) area in Russia, related actions to stipulate tasks in developing the State System of Accounting for and Control of Nuclear Materials (SSAC) and a role of the Federal Nuclear and Radiation Safety Authority of Russia (Gosatomnadzor) in this process is presented. Main principles, elements and practical results of Gosatomnadzor inspection activities are reported. Elements of the SSAC, status of works in establishment of the SSAC and in implementation of fragments of the SSAC, an international assistance in up-grading MC and A systems at some of the Russian facilities and in establishing the SSAC in Russia is outlined. (author)

Nuclear material operations manual

International Nuclear Information System (INIS)

Tyler, R.P.

1981-02-01

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

Nuclear material operations manuals

International Nuclear Information System (INIS)

Tyler, R.P.

1979-06-01

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

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

International Nuclear Information System (INIS)

1996-01-01

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

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

International Nuclear Information System (INIS)

Strezov, A.

1998-01-01

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

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

International Nuclear Information System (INIS)

1977-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2017-07-01

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

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

International Nuclear Information System (INIS)

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

2017-01-01

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

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

International Nuclear Information System (INIS)

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

2004-01-01

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

Evaluation and development of advanced nuclear materials: IAEA activities

International Nuclear Information System (INIS)

Inozemtsev, V.; Basak, U.; Killeen, J.; Dyck, G.; Zeman, A.; )

2011-01-01

structural materials' and 'Various issues related to thorium fuel cycle for thermal and fast reactors ' (all planned for 2011). Information is also provided about projects aimed at sharing experience in advances in the operation of existing nuclear units, such as on fuel modelling at high burn-ups, analysis of fuel failures, data bases development and training programmes. (author)

Nuclear material management: challenges and prospects

International Nuclear Information System (INIS)

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

2008-01-01

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

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

International Nuclear Information System (INIS)

Byeon, Kee Hoh; Kim, Ho Dong; Song, Dae Yong; Ko, Won Il; Hong, Jong Sook; Lee, Byung Doo

1999-07-01

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

A system of nuclear material accountancy in the JAERI

International Nuclear Information System (INIS)

Kase, Toshio; Nishizawa, Satoshi; Takahashi, Yoshindo

1983-05-01

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

Nuclear material operations manual

International Nuclear Information System (INIS)

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

1978-04-01

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

Nuclear measurements and reference materials

International Nuclear Information System (INIS)

1988-01-01

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

Nuclear material enrichment identification method based on cross-correlation and high order spectra

International Nuclear Information System (INIS)

Yang Fan; Wei Biao; Feng Peng; Mi Deling; Ren Yong

2013-01-01

In order to enhance the sensitivity of nuclear material identification system (NMIS) against the change of nuclear material enrichment, the principle of high order statistic feature is introduced and applied to traditional NMIS. We present a new enrichment identification method based on cross-correlation and high order spectrum algorithm. By applying the identification method to NMIS, the 3D graphs with nuclear material character are presented and can be used as new signatures to identify the enrichment of nuclear materials. The simulation result shows that the identification method could suppress the background noises, electronic system noises, and improve the sensitivity against enrichment change to exponential order with no system structure modification. (authors)

Nuclear materials management procedures

International Nuclear Information System (INIS)

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

1987-10-01

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

Material input of nuclear fuel

International Nuclear Information System (INIS)

Rissanen, S.; Tarjanne, R.

2001-01-01

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

Regulatory Framework for the Safe and Secure Transport of Nuclear Material in Japan

International Nuclear Information System (INIS)

Konnai, A.; Shibasaki, N.; Ikoma, Y.; Kato, M.; Yamauchi, T.; Iwasa, T.

2016-01-01

Regulations for nuclear material transport in Japan are based on international regulations. Safety and security regulations, however, have sometime different aspects which have caused a conflict of operations. This paper aims to introduce framework of safety and security regulations for nuclear material transport in Japan, and shows some issues in cooperation of these regulations. (author)

Security of a nuclear material in an installation is determined by how far the installation is to assure that nuclear material remains at a predetermined location

International Nuclear Information System (INIS)

Djoko Hari Nugroho

2010-01-01

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

Activities of the Nuclear Regulatory Authority of the Slovak Republic and safety of nuclear facilities in the Slovak Republic in 1994

International Nuclear Information System (INIS)

1995-01-01

The report summarizes activities of the Nuclear Regulatory Authority of the Slovak Republic (NRA SR) in 1994 and briefly presents results of the national expert supervision over nuclear safety facilities in the SR in 1994. In 1994, the NRA SR have performed a national supervision of following organizations: SE, a.s. - Jaslovske Bohunice Nuclear Power Plant (V-1 Nuclear Power Plant (V-1 NPP), V-2 Nuclear Power Plant (V-2 NPP), A-1 Nuclear Power Plant (A-1 NPP)); Mochovce Nuclear Power Plant; Radioactive waste repository, Mochovce); Organizations providing a specialized training of NPP personnel; Organizations providing specific deliveries and activities for the nuclear power industry; Organizations having an owner of nuclear materials; Organizations providing activities related to import of radioactive sources; Organizations using radioactive sources. Organization structure of the NRA SR is explained. In the presented Chapter 1 - Safety of nuclear power plants in the Slovak Republic - safety aspects of the Slovak NPPs are reported. The next activities are reported: nuclear materials and safeguards; radioactive waste; emergency planning and NRA SR's control and crisis centre; international activities to improve the national surveillance quality; other activities

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

International Nuclear Information System (INIS)

Roumiantsev, A.N.; Ostroumov, Y.A.; Whiteson, R.; Seitz, S.L.; Landry, R.P.; Martinez, B.J.; Boor, M.G.; Anderson, L.K.; Gary, S.P.

1997-01-01

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

Prevention of nuclear fuel cladding materials corrosion

International Nuclear Information System (INIS)

Yang, K.R.; Yang, J.C.; Lee, I.C.; Kang, H.D.; Cho, S.W.; Whang, C.K.

1983-01-01

The only way which could be performed by the operator of nuclear power plant to minimizing the degradation of nuclear fuel cladding material is to control the water quality of primary coolant as specified standard conditions which dose not attack the cladding material. If the water quality of reactor coolant does not meet far from the specification, the failure will occure not only cladding material itself but construction material of primary system which contact with the coolant. The corrosion product of system material are circulate through the whole primary system with the coolant and activated by the neutron near the reactor core. The activated corrosion products and fission products which released from fuel rod to the coolant, so called crud, will repeate deposition and redeposition continuously on the fuel rod and construction material surface. As a result we should consider heat transfer problem. In this study following activities were performed; 1. The crud sample was taken from the spent fuel rod surface of Kori unit one and analized for radioactive element and non radioactive chemical species. 2. The failure mode of nuclear fuel cladding material was estimated by the investigation of releasing type of fission products from the fuel rod to the reactor coolant using the iodine isotopes concentration of reactor coolants. 3. A study was carried out on the sipping test results of spent fuel and a discussion was made on the water quality control records through the past three cycle operation period of Kori unit one plant. (Author)

ANCRE alliance: Road-map for nuclear materials

International Nuclear Information System (INIS)

Touboul, F.; Carre, F.

2013-01-01

targets have changed: more severe operating conditions (higher neutron fluence and very high temperature), and new objectives for reliability and security, in order to prevent and safely manage external aggressions (earthquake, aircraft impact, etc.) and severe internal accidents. Manufacturers and researchers must rely on robust methods to assess and justify the lifetime of existing nuclear reactors, and to develop new materials (incrementally or leapfrogging) for current and future nuclear systems. Priority objectives have been defined by ANCRE members and subsequent scientific locks have been determined, leading to program proposals: material for reactor vessel or internal circuits, corrosion mechanisms, zirconium alloys, fuel materials, nano-reinforced steels, surface engineering, advanced metallurgical processes, composite materials, materials for fusion, refractory materials, containment materials (concrete, glass, clay), structural mechanics, multi-scale modeling and simulation, experiments. At the same time they recommend directions for cooperative research, ANCRE road-maps also identify existing laboratories able to contribute to these research goals, and suggest new research clusters or structures when appropriate, as well as other frameworks of cooperation at national, European or international level. ANCRE also recommends initiatives to tighten links between research and education. ANCRE road-map on materials for nuclear energies fully concurs that multi-scale and multi-physics modeling and simulation tools based on the most accurate knowledge of physicochemical phenomena at various scales, together with characterization tools at the same scales, are of crucial importance for predicting materials performance and lifetime in service conditions, and for guiding research on materials for future nuclear systems. (authors)

Statistical methods for nuclear material management

International Nuclear Information System (INIS)

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

1988-12-01

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

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.

Materials for generation-IV nuclear reactors

International Nuclear Information System (INIS)

Alvarez, M. G.

2009-01-01

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)

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

International Nuclear Information System (INIS)

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

1978-05-01

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

Annual Report 2013. Nuclear Regulatory Authority

International Nuclear Information System (INIS)

2010-01-01

The present Annual Report of Activities of the Nuclear Regulatory Authority (ARN), prepared regularly from the creation as independent institution, describes across seven parts and eight annexes the activities developed by the organism during 2013. The main topic are: the organization and the activity of the ARN; the regulatory standards; the licensing and inspection of nuclear power plants and critical facilities; the emergency systems; the environmental monitoring; the occupational surveillance; the training and the public information; improved organizational and budgetary developments. Also, this publication has annexes with the following content: regulatory documents; inspections to medical; presentations of publications from ARN staff; measurement and evaluation of the drinking water of Ezeiza; international expert report on the implementation of international standards on radiation protection in the Ezeiza Atomic Center; Code of Ethics of the Nuclear Regulatory Authority.

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1966-02-15

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

The French Nuclear Safety Authority - ASN

International Nuclear Information System (INIS)

2013-01-01

The ASN (Nuclear Safety Authority) was created by the act of 13 June 2006 concerning the transparency and safety of nuclear activities. The ASN is an independent administrative body that is in charge of controlling nuclear activities in France. The ASN has a workforce of 471 people and a budget of about 76 millions euros. This article details its missions and how it is organized to cover all the French territory. (A.C.)

Separation of gallium and actinides in plutonium nuclear materials by extraction chromatography

International Nuclear Information System (INIS)

Eitrheim, E.S.; Knight, A.W.

2015-01-01

Analysis of stable gallium in nuclear materials has applications in nuclear fuel characterization and nuclear forensics. The use of positron-emitting gallium isotope 68 Ga as a tracer for Ga recoveries for analyses in materials containing actinides was explored. A radiochemical method for the separation of Ga, Pu, U, Th, and Am using commercially-available extraction chromatography resins was developed and evaluated. The method effectively allows precise determination of Ga yield (97 ± 3 %) in the analysis of stable Ga (spike recovery 101 ± 1 %) and radioactive Pu (radiochemical yield, 82 ± 10 %; spike recovery, 96 ± 3 %), while also providing pure elemental fractions of other actinides relevant to materials encountered in the analysis Pu-containing materials. (author)

Mobile Techniques for Rapid Detection of Concealed Nuclear Material

International Nuclear Information System (INIS)

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

2015-01-01

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

Steps to implement the legal and regulatory infrastructure for physical protection of nuclear material in Peru

International Nuclear Information System (INIS)

Ramirez Quijada, R.

2001-01-01

Full text: The signature of Peru to become part of the Convention of Physical Protection of Nuclear Material in 1995 has implied an obligation to formalize the legal and regulatory infrastructure for this purpose. As first step, physical protection measures were formalized on the two nuclear facilities: one critical assembly of zero power (RP0) and another research reactor of 10 Mw thermal power (RP10). Both of the installations use low enriched uranium nuclear fuel (Material and Testing Material - MTR type). On the other side, even thorium was put in perspective to control; currently it is being used for non-nuclear purposes and has not been included inside the physical protection measures. Its physical and chemical form and its small quantity do not warrant for applying the Convention. The physical protection measures implemented in the research reactor are well depicted and it is concluded that the physical protection system meets the recommendations of INFCIRC/225/Rev.3. The critical facility (RP0), as having nuclear material categorized III, has implemented a less restrictive system but enough to meet the requirements. In 1999 an evaluation of all physical protection systems was performed for these two nuclear installations. This evaluation took into account the recommendations of INFCIRC/225/Rev.4. The general conclusion was that the performance of physical protection system was suitable to the categories of nuclear material - II and III - and that the installations where nuclear material is used were suitably protected against non-authorized or illegal removal of nuclear material and sabotage. However, some of components of the system were not appropriately working and could make all of the system weak. Another of the identified problems was the lack of a rule on physical protection and also the lack of the Design Basis Threat, although this fact was well known due the social conditions in the country. The second undertaking has been to prepare the rule on

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

International Nuclear Information System (INIS)

1981-01-01

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

Computational modeling of the behavior of nuclear materials (2). Molecular simulations for nuclear materials. Current situation and future perspective

International Nuclear Information System (INIS)

Okita, Taira; Itakura, Mitsuhiro

2017-01-01

Molecular simulations for nuclear materials aim to reproduce atomistic-scale phenomena induced by irradiation and infer the change in material properties. In the present work, recent progress in this field is presented. In particular, the following three topics are explained: (1) Quantification of lattice defects formation process induced by fast neutron collision. (2) Identification of dislocation-channeling mechanism induced by interactions between defect clusters and dislocations. (3) Modeling of the three dimensional movement of defect clusters using molecular dynamics and kinetic Monte Carlo simulations. (author)

Content Development, Presentation and Delivery for eLearning in Nuclear Science and Engineering: Experiences with Emerging Authoring Tools

International Nuclear Information System (INIS)

Bamford, S.; Afriyie, P.; Comlan, E.

2016-01-01

Full text: Transference of explicit knowledge starts from content development, and proceeds with packaging and delivery. A comparative study of some selected authoring tools for knowledge creation in Nuclear Sciences and Engineering education is being carried out at the School of Nuclear and Allied Sciences in Accra, Ghana. These authoring tools include commercial software (Macromedia Suite CS6, Learning 6.0) as well as freeware software (Xerte, eXe). A course, X-ray Fluorescence Spectrometry (NSAP 603), at the postgraduate School of Nuclear and Allied Sciences (SNAS), has been selected for migration onto an eLearning platform. Different authoring tools have been employed to create some ICT-based modules for teaching and learning. This paper therefore shares the experiences realized in moving from course syllabus to digitized modules, integrating pedagogical considerations, the strengths and weakness of the selected authoring tools, user-interactivity and usability of the modules produced. The need and the basis for the adoption of an appropriate authoring tool for creation of scientific, mathematical, and engineering documents and learning materials has also been discussed. Leveraging on ICT to produce pedagogically sound learning materials for eLearning platforms promotes interests of students in nuclear sciences, and ensures continuity in producing qualified professionals. (author

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

Science.gov (United States)

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

2013-11-01

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

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

International Nuclear Information System (INIS)

Kondratov, S.I.

1998-01-01

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

Nuclear Safety Authority independence, progresses to be considered

International Nuclear Information System (INIS)

Delzangles, Hubert

2013-01-01

The Nuclear Safety Authority is an independent administrative body. Nevertheless, functional and organic independence from operators and government can have different degrees. Having a look on the actual context, where government holds a large part of the main nuclear French operators, independence has to be maximal in order to avoid any conflict of interest that could attempt to nuclear safety. In a global point of view, it is possible to think about the risks or the benefits of the institutionalized cooperation between national regulators on the necessary independence of the Nuclear Safety Authority

Advanced research workshop: nuclear materials safety

International Nuclear Information System (INIS)

Jardine, L J; Moshkov, M M.

1999-01-01

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

Experience in safeguarding nuclear material at the Rheinsberg nuclear power station

International Nuclear Information System (INIS)

Winkler, R.

1976-01-01

The three years' experience that has been gained in application of the Safeguards Agreement shows that the carrying out of inspections at the nuclear power plant has virtually no effect on operating conditions. In future it will be possible to reduce this effect even further and still maintain the operational reliability of the station. Verification of the transfer of nuclear material and detection of possible violations have proved relatively simple. The labour requirement of each unit at the station for the performance of inspections is not more that thirty man-days. Constructive collaboration between power station staff and inspectors is of great importance in improving the safeguards procedures. (author)

Control system and nuclear materials inventory at IPEN/CNEN-SP, Brazil

International Nuclear Information System (INIS)

Araujo, Jose Adroaldo de; Enokihara, Cyro Teiti

2002-01-01

The history, requirements, organization, and operation of the State System of Accounting and Control from the Institute for Energetic and Nuclear Research (IPEN-CNEN/SP) are described. The implementation system at the institution take into consideration the national and international safeguards requirements. It has started by the nuclear material (U, Pu and Th) physical inventory taking, including their provenance and transformation. The earlier computerized accounting system used for control has been replaced by a new one developed by the National Authority (CNEN/CSG). The optimized system has more flexibility, giving a more effective answer to any occurred change on Material Balance Area. The present system make use of an effective methodology. (author)

Transcending sovereignty. In the management and control of nuclear material

International Nuclear Information System (INIS)

Scheinman, Lawrence

2001-01-01

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

Nuclear material attractiveness: an assessment of material associated with a closed fuel cycle

International Nuclear Information System (INIS)

Bathke, C.G.; Wallace, R.K.; Hase, K.R.; Jarvinen, G.D.; Ireland, J.R.; Johnson, M.W.; Ebbinghaus, B.B.; Sleaford, B.W.; Robel, M.; Bradley, K.S.; Collins, B.A.; Prichard, A.W.; Smith, B.W.

2010-01-01

This paper examines the attractiveness of materials mixtures containing special nuclear materials (SNM) associated with the various processing steps required for a closed fuel cycle. This paper combines the results from earlier studies that examined the attractiveness of SNM associated with the processing of spent light water reactor (LWR) fuel by various reprocessing schemes and the recycle of plutonium as a mixed oxide (MOX) fuel in LWR with new results for the final, repeated burning of SNM in fast-spectrum reactors: fast reactors and accelerator driven systems (ADS). The results of this paper suggest that all reprocessing products evaluated so far need to be rigorously safeguarded and provided moderate to high levels of physical protection. These studies were performed at the request of the United States Department of Energy (DOE), and are based on the calculation of 'attractiveness levels' that has been couched in terms chosen for consistency with those normally used for nuclear materials in DOE nuclear facilities. The methodology and key findings will be presented. Additionally, how these attractiveness levels relate to proliferation resistance (e.g. by increasing impediments to the diversion, theft, or undeclared production of SNM for the purpose of acquiring a nuclear weapon), and how they could be used to help inform policy makers, will be discussed. (authors)

Uncertainty estimation in nuclear material weighing

Energy Technology Data Exchange (ETDEWEB)

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

2011-12-15

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

Central eastern Europe approach to the security over nuclear materials

International Nuclear Information System (INIS)

Smagala, G.

2002-01-01

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

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

International Nuclear Information System (INIS)

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

2008-01-01

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

The Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC) as safeguard regional agency

International Nuclear Information System (INIS)

Alvim, C.F.

1994-01-01

The Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials - ABACC applies regional safeguards on nuclear materials in Brazil and Argentina. The framework of international agreements concerning ABACC is presented, and the characteristics and requirements that a regional nuclear safeguards organization must fulfill are discussed. (author). 2 refs, 1 tab

The nuclear safety authority (ASN) presents its report on the status of nuclear safety and radiation protection in France in 2010

International Nuclear Information System (INIS)

2011-01-01

After a presentation of the French nuclear safety authority (ASN) and of some events which occurred in 2010, this report present the actions performed by the ASN in different fields: nuclear activities (ionizing radiations and risks for health and for the environment), principles and actors of control of nuclear safety, radiation protection and environment protection, regulation, control of nuclear activities and of exposures to ionizing radiations, emergency situations, public information and transparency, international relationship. It proposes a regional overview of nuclear safety and radiation protection in France. It addresses the activities controlled by the ASN: medical and non medical usages of ionizing radiations, transportation of radioactive materials, electronuclear power stations, installations involved in the nuclear fuel cycle, research nuclear installations and other nuclear installations, safety in basic nuclear installation dismantling, radioactive wastes and polluted sites

The Physical Protection of Nuclear Material and Nuclear Facilities

International Nuclear Information System (INIS)

1999-08-01

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

The Physical Protection of Nuclear Material and Nuclear Facilities

International Nuclear Information System (INIS)

1999-06-01

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

The Physical Protection of Nuclear Material and Nuclear Facilities

International Nuclear Information System (INIS)

1999-06-01

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

Activities of Nuclear Regulatory Authority and safety of nuclear facilities in the Slovak Republic in 1993

International Nuclear Information System (INIS)

1994-04-01

A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (NRA SR) in 1993 is presented. These activities are reported under the headings: (1) Introduction; (2) Regulatory activities at nuclear power plants units in operation; (2.1) Nuclear power plant SEP-EBO V-1; (4) Selected operation events and safety assessment in NPP SEP-EBO V-1; (2.2) Safety assessment of NPP SEP-EBO V-2; (3) Results of regulatory activities at the decommissioning of NPP A-1; (4) Regulatory activities at units under construction SEP-EMO - NPP Mochovce; (5) Further regulatory activities. (5.1) Preparation of designated personnel; (5.2) Inspection and accountancy of nuclear material; (5.3) Security provisions; (5.4) Accounted items and double use items; (5.5) Problem of radioactive wastes; (6.1) International co-operation activities of NRA; (6.2) Emergency planning; (6.3) International activities for quality enhancement of national supervision; (7) Conclusion [sk

Nuclear materials stewardship: Our enduring mission

International Nuclear Information System (INIS)

Isaacs, T.H.

1998-01-01

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

Public and media acceptance of nuclear materials transport

International Nuclear Information System (INIS)

Lindeman, E.

1999-01-01

Transport is absolutely essential to the continued existence of a nuclear industry that includes large-scale power generation, sophisticated research, and medicine. Indeed, transport of nuclear materials is hardly a new business. What is new is the public's awareness and distrust of this transport - a distrust fuelled by the well-funded and skilled manipulation of the nuclear industry's detractors. The nuclear industry itself has only recently begun to acknowledge the importance and the implications of transport. This paper looks at the public and media response to the European-Japanese and the US Department of Energy's transport campaigns and quotes from several telling newspaper articles. It emphasizes the need for the nuclear industry to continue to be vigilant in its efforts to reach the public, media and governments with good science, openness and well-communicated facts. (author)

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

International Nuclear Information System (INIS)

Bezak, S.

2001-01-01

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

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.

Accountability of Radioactive Materials in Malaysian Nuclear Agency

International Nuclear Information System (INIS)

Noor Fadilla Ismail; Wan Saffiey Wan Abdullah; Khairuddin Mohamad Kontol; Azimawati Ahmad; Suzilawati Muhd Sarowi; Mohd Fazlie Abdul Rashid

2016-01-01

Radioactive materials possessed in Malaysian Nuclear Agency have many beneficial applications for research and development, calibration, tracer and irradiation. There are two types of radioactive materials which consist of sealed sourced and unsealed sourced shall be accounted for and secured at all the times by following the security aspect. The Health Physics Group in the Department of Radiation Safety and Health Division is responsible to manage the issues related to any accountability for all radioactive material purchased or received under the radioactive material protocol. The accountability of radioactive materials in Malaysian Nuclear Agency is very important to ensure the security and control the radioactive materials to not to be lost or fall into the hands of people who do not have permission to possess or use it. The accountability of radioactive materials considered as a mandatory to maintaining accountability by complying the requirements of the Atomic Energy Licensing Act 1984 (Act 304) and regulations made thereunder and the conditions of license LPTA / A / 724. In this report describes the important element of accountability of radioactive materials in order to enhances security standard by allowing tracking of the locations of sources and to reduce the risk of radioactive materials falling into the wrong hands. (author)

A sensitive detector to prevent smuggling of nuclear material

International Nuclear Information System (INIS)

Bock, H.; Rost, R.; Miller, B.R.

1995-01-01

A drive through detector systems using four plastic scintillators and associated electronics for the detections of small amounts or uranium or plutonium in cars is described. The system has been calibrated with various sample of special nuclear material and the lower detection limits are presented. (author)

Development and implementation of methods for determination of the origin of nuclear materials

International Nuclear Information System (INIS)

Wallenius, M.; Pajo, L.; Mayer, K.

2001-01-01

The determination of the origin of seized nuclear material is important for authorities in the context of the criminal investigation, in order to return the material to its last legal owner and to help preventing any further diversion of material from this source. Origin determination is based on a complex pattern of parameters obtained through analytical measurements. The information required to determine the origin of nuclear materials may be divided into two categories: endogenous information (e.g. age or mode of production of the material) which is self-explanatory; whereas exogenous information (e.g. dimensions, surface roughness, impurities) requires a database to which the parameters can be compared. The Institute for Transuranium Elements has developed methods to determine characteristic parameters like impurities, surface roughness, or microstructural information. Furthermore, a database was set up containing relevant information on reactor fuels. (author)

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

International Nuclear Information System (INIS)

1977-01-01

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

Nuclear Materials: Reconsidering Wastes and Assets - 13193

International Nuclear Information System (INIS)

Michalske, T.A.

2013-01-01

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)

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

International Nuclear Information System (INIS)

2002-01-01

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

Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1994 ed

International Nuclear Information System (INIS)

1994-08-01

This is the fifth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM). The reporting format was established at consecutive meetings of SAGSTRAM, whose membership consists of national competent authorities responsible for the transport of radioactive material from those Member States who have a nuclear industry and others who have shown a keen interest in the IAEA's transport safety programme. Through the PACKTRAM database, the Secretariat collects administrative and technical information on package approval certificates to assist national competent authorities in regulating radioactive material movements in their country. The database carries information on extant certificates and those that expired within the last two complete calendar years. The 1985 Edition of IAEA Safety Series No. 6, the ''Regulations for the Safe Transport of Radioactive Material'' highlights the role of competent authorities in assuring regulatory compliance in their own countries. Package approval certificates are an important aspect of that function. This document aims to be a useful reference for competent authorities as well as for manufacturers and shippers of radioactive material

Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1995 edition

International Nuclear Information System (INIS)

1995-09-01

This is the sixth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM). The reporting format was established at consecutive meetings of SAGSTRAM, whose membership consists of national competent authorities responsible for the transport of radioactive material from those Member States who have a nuclear industry and others who have shown a keen interest in the IAEA's transport safety programme. Through the PACKTRAM database, the Secretariat collects administrative and technical information on package approval certificates to assist national competent authorities in regulating radioactive material movements in their country. The database carries information on extant certificates and those that expired within the last complete calendar year. The 1985 Edition of IAEA Safety Series No. 6, the ''Regulations for the Safe Transport of Radioactive Material'' highlights the role of competent authorities in assuring regulatory compliance in their own countries. Package approval certificates are an important aspect of that function. This document aims to be a useful reference for competent authorities as well as for manufacturers and shippers of radioactive material. 6 tabs

Nuclear safety authority. Strategical planning 2005- 2007

International Nuclear Information System (INIS)

Anon.

2006-01-01

The Nuclear safety Authority (A.S.N.) provides, in the name of the state, the monitoring of nuclear safety and radiation protection to protect workers, patients, public and environment from the risks in relation with nuclear activities and more broadly with ionizing radiations, it contributes to citizens information in these areas. The ambition of A.S.N. is to carry out a successful, legitimate, credible nuclear monitoring, recognized by citizens and that constitutes an international reference. (N.C.)

Thermodynamics of nuclear materials

International Nuclear Information System (INIS)

Rand, M.H.

1975-01-01

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

STUDY ON STATE SYSTEMS OF ACCOUNTING AND CONTROL OF NUCLEAR MATERIALS IN SOME COUNTRIES

International Nuclear Information System (INIS)

ZIDAN, W.I.; EL-GAMMAL, W.A.

2008-01-01

All Safeguards agreements between the International Atomic Energy Agency (IAEA) and its Member States require the State to establish and maintain a system of accounting for and control of nuclear material subject to safeguards (SSAC) in order to keep track on nuclear materials subject to such agreements. SSACs implementation in 34 IAEA member States varying in their size of nuclear activities, international treaties and nuclear power plants ownership were studied. The study is oriented to state legal framework, SSAC authority, dependency, objectives and functions

Development of DUPIC safeguards technology; development of web based nuclear material accounting program

Energy Technology Data Exchange (ETDEWEB)

Kim, J. T.; Choi, S. H.; Choi, S. J. [Kongju National University, Kongju (Korea)

2002-04-01

The purpose of this project is to develop the web-based digital image processing system with the client/server architecture based on TCP/IP to be able to search and manage image data at the remote place. This system provides a nuclear facility with the ability to track the movement of nuclear material and to control and account nuclear material at anywhere and anytime. Also, this system will be helpful to increase the efficiency of safeguards affairs. The developed web-based digital image processing system for tracking the movement of nuclear material and MC and A can be applied to DUPIC facility. The result of this project will eventually contribute to similar nuclear facilities as well as the effective implementation of DUPIC safeguards. In addition, it will be helpful to enhance international confidence build-up in the peaceful use of spent fuel material. 15 refs., 33 figs., 4 tabs. (Author)

Global nuclear material flow/control model

International Nuclear Information System (INIS)

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

1997-01-01

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

Techniques and methods in nuclear materials traceability

International Nuclear Information System (INIS)

Persiani, P.J.

1996-01-01

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

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

International Nuclear Information System (INIS)

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

1976-01-01

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

The declaration regime: An efficient tool to improve control and protection of nuclear materials in France

International Nuclear Information System (INIS)

Pillette-Cousin, L.

2001-01-01

Full text: The French Government set up a national safeguards system under the authority of the Ministry for Industry to control nuclear materials within national boundaries and to ensure physical protection for nuclear materials, even for the small quantities held by users in industrial, medical and research areas. The main nuclear materials detained by small owners are depleted uranium and thorium. These materials are present in manufactured equipment (radiation shielding in industrial gammagraphy and radiotherapy, collimation devices and other accessories) which are used or unused, which may be damaged or left as scraps. The French protection and control system of nuclear materials is an original system based on detailed and comprehensive regulations, taking into account in a specific way the small users of nuclear materials. The decree no. 81-512 of 12 May 1981 establishes three different regimes: licensing, declaration and exemption, according to the nature and quantity of nuclear materials involved. Typically, the declaration regime applies to quantities of depleted uranium or thorium, greater than 1 kg and lower than 500 kg. The Order of 14 March 1984 sets the requirements related to the control and physical protection of nuclear materials in the frame of the declaration regime. A declaration must be established every year by the operator and sent to the IPSN, acting as technical support body of the national authority. This declaration provides the stock of all nuclear materials held by the operator and stock variations occurred during the previous year, including the identification of senders and receivers. Before fulfilling its annual declaration, the operator must carry out a physical inventory of all nuclear material, both used and unused. The declaration also describes the main features concerning facility layout related to surveillance and physical protection of materials. With respect to physical protection requirements, nuclear materials should be

Security programs for Category I or II nuclear material or certain nuclear facilities. Regulatory guide G-274

International Nuclear Information System (INIS)

2003-03-01

The purpose of this regulatory guide is to help applicants for a Canadian Nuclear Safety Commission (CNSC) licence in respect of Category I or II nuclear material - other than a licence to transport - , or a nuclear facility consisting of a nuclear reactor that may exceed 10 MW thermal power during normal operation, prepare and submit the security information to be included with the application, pursuant to the Nuclear Safety and Control Act (NSCA). Category I and II nuclear material are defined in Appendix B to this guide. This guide describes: the security information that should typically be included with the application for any licence referred to above; how the security information may be organized and presented in a separate document (hereinafter 'the security program description'), in order to assist CNSC review and processing of the application; and, the administrative procedures to be followed when preparing, submitting or revising the security program description. (author)

Nuclear energy and materials in the 21st century

International Nuclear Information System (INIS)

Krakowski, R.A.; Davidson, J.W.; Bathke, C.G.; Arthur, E.D.; Wagner, R.L. Jr.

1997-01-01

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 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 (∼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 results reported examine departures from a ''basis scenario'' and are presented in the following order of increasing specificity: a) definition and parametric variations 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. (author)

Border Control of Nuclear and Other Radioactive Materials

International Nuclear Information System (INIS)

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

2007-01-01

In the second half of year 2006, stationary detection systems for nuclear and other radioactive materials were installed on Border Crossing Bregana, Croatia. Yantar 2U, which is the commercial name of the system, is integrated automatic system capable of detection of nuclear and other radioactive materials prepared for fixed-site customs applications (Russian origin). Installed system contains portal monitors, camera, communication lines and communication boxes and server. Two fully functional separate systems has been installed on BC Bregana, one on truck entrance and another one on car entrance. In this article the operational experience of installed system is presented. This includes statistical analysis of recorded alarms, evaluation of procedures for operational stuff and maintenance and typical malfunction experience, as well as some of the recommendation for future use of detection systems.(author)

Criminal offences considered in the Convention on the Physical Protection of Nuclear Material

International Nuclear Information System (INIS)

Neira, C.C.

1996-01-01

The Convention on the Physical Protection of Nuclear Material was signed in Vienna, on April 3, 1980, approved by Law 23.620 on September 28, 1998, and published in the Official Bulletin of the Argentine Republic on November 2, 1988. This Convention considers some aspects of Criminal Law and Criminal Procedural Law and integrates the normative hierarchical structure of the article 31 of the National Constitution. The adequacy of this Convention to the Argentine law is considered through two aspects: The first one examines figures existing in the Argentine Legislation about larceny and robbery of nuclear materials, misappropriation of nuclear materials, obtainment and fraud of nuclear materials, exaction through threat or intimidation, etc., which are considered in different articles of the Argentine Criminal Law. The second one analyses behaviours not foreseen in the Criminal Law and which are not qualified by the current Argentina's Criminal Code, such as exaction of nuclear material through the use of violence, the international perpetration of an act consisting to receive, possess, use, vacate, scatter nuclear material without legal authorization, or in the case that the act causes death, serious injuries to persons and others. The purpose of the future enactment of a new Nuclear Law is to put in order and fill-in gaps referred to different aspects such as civil liability in nuclear damages, characteristics of the nuclear damages, etc [es

Control of nuclear material specified equipment and specified material

International Nuclear Information System (INIS)

1982-04-01

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

Development of comprehensive material performance database for nuclear applications

International Nuclear Information System (INIS)

Tsuji, Hirokazu; Yokoyama, Norio; Tsukada, Takashi; Nakajima, Hajime

1993-01-01

This paper introduces the present status of the comprehensive material performance database for nuclear applications, which was named JAERI Material Performance Database (JMPD), and examples of its utilization. The JMPD has been developed since 1986 in JAERI with a view to utilizing various kinds of characteristics data of nuclear materials efficiently. Management system of relational database, PLANNER, was employed, and supporting systems for data retrieval and output were expanded. In order to improve user-friendliness of the retrieval system, the menu selection type procedures have been developed where knowledge of the system or the data structures are not required for end-users. As to utilization of the JMPD, two types of data analyses are mentioned as follows: (1) A series of statistical analyses was performed in order to estimate the design values both of the yield strength (Sy) and the tensile strength (Su) for aluminum alloys which are widely used as structural materials for research reactors. (2) Statistical analyses were accomplished by using the cyclic crack growth rate data for nuclear pressure vessel steels, and comparisons were made on variability and/or reproducibility of the data between obtained by ΔK-increasing and ΔK-constant type tests. (author)

Technical limitations of nuclear fuel materials and structures

International Nuclear Information System (INIS)

Hansson, L.; Planman, T.; Vitikainen, E.

1993-05-01

This report gives a summary of the tasks carried out within the project 'Technical limitations of nuclear fuel materials and structures' which belongs to the Finnish national research programme called 'Systems behaviour and operational aspects of safety'. The duration of the project was three years from 1990 to 1992. Most western LWR utilities, including the two Finnish ones have an incentive to implement extended burnup fuel cycles in their nuclear power plants. The aim of this project has been authorities to support them in the assessment and licensing of new fuel designs and materials. The research work of the project was focused on collecting and qualifying fuel performance data and on performing laboratory tests on fresh and irradiated cladding and structural materials. Moreover, knowledge of the high burnup phenomena was obtained through participation in international research projects such as OECD Halden Project and several Studsvik projects. Experimental work within the framework of the VVER fuel cooperative effort was also continued. (orig.)

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

International Nuclear Information System (INIS)

Pei Junchen; Xu Furong; Zheng Chunkai

2003-01-01

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

United States Department of Energy Nuclear Materials Stewardship

International Nuclear Information System (INIS)

Newton, J. W.

2002-01-01

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

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

International Nuclear Information System (INIS)

Reistad, O.; Maerli, M.

1998-01-01

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

Implementation of the INSPECT software package for statistical calculation in nuclear material accountability

International Nuclear Information System (INIS)

Marzo, M.A.S.

1986-01-01

The INSPECT software package was developed in the Pacific Northwest Laboratory for statistical calculations in nuclear material accountability. The programs apply the inspection and evaluation methodology described in Part of the Safeguards Technical Manual. In this paper the implementation of INSPECT at the Safeguards Division of CNEN, and the main characteristics of INSPECT are described. The potential applications of INSPECT to the nuclear material accountability is presented. (Author) [pt

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

International Nuclear Information System (INIS)

1980-01-01

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

The research on the material management system in nuclear power plant construction process

International Nuclear Information System (INIS)

Liu Xuegeng; Huang Zhongping

2010-01-01

According to the module construction speciality of nuclear power plant, this article analyzes the relationship between the actual amount of the material transported to the construction site and the planed needs of the material, and points out the zero inventory management target in the nuclear power plant construction site. Based on this, the article put forward a nuclear power plant material management system which is based on the 'pull' information driver. This system is composed by material coding sub-system, procurement and site material integrated management sub-system and project control sub-system, and is driven by the material demand from construction site to realize the JIT purchasing. This structure of the system can reduce the gap between the actual amount of the material transported to the site and the planed needs of the material and achieve the target of reducing storage at construction site. (authors)

The physical protection of nuclear material

International Nuclear Information System (INIS)

1989-12-01

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

Technology development for nuclear material accountability

International Nuclear Information System (INIS)

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

1991-03-01

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

Responsibilities of nuclear regulatory authority and overview of nuclear safety regulations in Slovakia

International Nuclear Information System (INIS)

Misak, J.

1996-01-01

The paper describes the organizational structure of the Nuclear Regulatory Authority of the Slovak Republic, its rights and duties, the status of nuclear legislation with emphasis on nuclear activities completely or partially covered, and licensing procedures

Quality control of three main materials for civil construction of nuclear power plant

International Nuclear Information System (INIS)

Wang Feng

2011-01-01

The construction and operation of nuclear power plant is a systematic engineering. To ensure quality and safety of nuclear power plants, each work from design to operation can have certain impact on the quality and safety of the project. The quality of each related work shall be controlled. Starting from the quality control over raw materials for the civil construction of nuclear power plant, this article mainly analyzes how to control the quality and manage the three main materials of steel, concrete and modular parts in the civil construction. (author)

Use of some nuclear methods for materials analysis

International Nuclear Information System (INIS)

Habbani, Farouk

1994-01-01

A review is given about the use of two nuclear-related analytical methods, namely: X-ray fluorescence (XRF) and neutron activation analysis (NAA), for the determination of elemental composition of various materials. Special emphasis is given to the use of XRF for the analysis of geological samples, and NAA for the analysis of food - stuffs for their protein content. (Author)

Foreign Material Exclusion Program at CNE Cernavoda Nuclear Generating Station

Energy Technology Data Exchange (ETDEWEB)

Urjan, Daniel [S.N. ' Nuclearelectrica' SA, CNE Cernavoda Nuclear Power Plant, Medgidiei 2 Street, 905200 Cernavoda, Constanta (Romania)

2008-07-01

In the face of a continuing attention to operations and maintenance costs at nuclear power plants, the future of the industry depends largely upon increasing plant availability and improving operating efficiency. The success in achieving these objectives is dependent upon the success of each plant's equipment maintenance program. Preventing the introduction of foreign materials into a nuclear power plant system or component requires a careful, thoughtful, and professional approach by all site personnel. This paper describes a proactive approach to prevent the introduction of foreign material into systems and components, by providing an overview of technical considerations required to develop, implement, and manage a foreign material exclusion program at CNE Cernavoda Unit 1 and 2 Nuclear Power Station. It is also described an example of Foreign Material Intrusion which happened during the 2003 planned maintenance outage at Cernavoda Unit no.1. This paper also defines personnel responsibilities and key nomenclature and a means for evaluating prospective work tasks and activities against standardized criteria, in order to identify the appropriate level of the required FME controls. (author)

Foreign Material Exclusion Program at CNE Cernavoda Nuclear Generating Station

Energy Technology Data Exchange (ETDEWEB)

Urjan, Daniel [S.N. ' Nuclearelectrica' SA, CNE Cernavoda Nuclear Power Plant, Medgidiei 2 Street, 905200 Cernavoda, Constanta (Romania)

2008-07-01

In the face of a continuing attention to operations and maintenance costs at nuclear power plants, the future of the industry depends largely upon increasing plant availability and improving operating efficiency. The success in achieving these objectives is dependent upon the success of each plant's equipment maintenance program. Preventing the introduction of foreign materials into a nuclear power plant system or component requires a careful, thoughtful, and professional approach by all site personnel. This paper describes a proactive approach to prevent the introduction of foreign material into systems and components, by providing an overview of technical considerations required to develop, implement, and manage a foreign material exclusion program at CNE Cernavoda Unit 1 and 2 Nuclear Power Station. It is also described an example of Foreign Material Intrusion which happened during the 2003 planned maintenance outage at Cernavoda Unit no.1. This paper also defines personnel responsibilities and key nomenclature and a means for evaluating prospective work tasks and activities against standardized criteria, in order to identify the appropriate level of the required FME controls. (author)

Foreign Material Exclusion Program at CNE Cernavoda Nuclear Generating Station

International Nuclear Information System (INIS)

Urjan, Daniel

2008-01-01

In the face of a continuing attention to operations and maintenance costs at nuclear power plants, the future of the industry depends largely upon increasing plant availability and improving operating efficiency. The success in achieving these objectives is dependent upon the success of each plant's equipment maintenance program. Preventing the introduction of foreign materials into a nuclear power plant system or component requires a careful, thoughtful, and professional approach by all site personnel. This paper describes a proactive approach to prevent the introduction of foreign material into systems and components, by providing an overview of technical considerations required to develop, implement, and manage a foreign material exclusion program at CNE Cernavoda Unit 1 and 2 Nuclear Power Station. It is also described an example of Foreign Material Intrusion which happened during the 2003 planned maintenance outage at Cernavoda Unit no.1. This paper also defines personnel responsibilities and key nomenclature and a means for evaluating prospective work tasks and activities against standardized criteria, in order to identify the appropriate level of the required FME controls. (author)

Advanced physical protection systems for nuclear materials

International Nuclear Information System (INIS)

Jones, O.E.

1976-01-01

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

International training course on nuclear materials accountability for safeguards purposes

International Nuclear Information System (INIS)

1980-12-01

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

International training course on nuclear materials accountability for safeguards purposes

Energy Technology Data Exchange (ETDEWEB)

1980-12-01

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

Hot cell works and related irradiation tests in fission reactor for development of new materials for nuclear application

International Nuclear Information System (INIS)

Shikama, Tatsuo

1999-01-01

Present status of research works in Oarai Branch, Institute for Materials Research, Tohoku University, utilizing Japan Materials Testing Reactor and related hot cells will be described.Topics are mainly related with nuclear materials studies, excluding fissile materials, which is mainly aiming for development of materials for advanced nuclear systems such as a nuclear fusion reactor. Conflict between traditional and routined procedures and new demands will be described and future perspective is discussed. (author)

Supplier responsibility for nuclear material quality

International Nuclear Information System (INIS)

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

1976-01-01

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

Current trends in nuclear material transportation

International Nuclear Information System (INIS)

Ravenscroft, Norman; Oshinowo, Franchone

1997-01-01

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

Corrosion degradation of materials in nuclear reactors and its control

International Nuclear Information System (INIS)

Kain, Vivekanand

2016-01-01

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

Nordic Nuclear Materials Forum for Generation IV Reactors

Energy Technology Data Exchange (ETDEWEB)

Anghel, C. (Studsvik Nuclear AB, Nykoeping (Sweden)); Penttilae, S. (Technical Research Centre of Finland, VTT (Finland))

2010-03-15

A network for material issues for Generation IV nuclear power has been initiated within the Nordic countries. The objectives of the Generation IV Nordic Nuclear Materials Forum (NOMAGE4) are to put the basis of a sustainable forum for Gen IV issues, especially focussing on fuels, cladding, structural materials and coolant interaction. Other issues include reactor physics, dynamics and diagnostics, core and fuel design. The present report summarizes the work performed during the year 2009. The efforts made include identification of organisations involved in Gen IV issues in the Nordic countries, update of the forum website, http://www.studsvik.se/GenerationIV, and investigation of capabilities for research within the area of Gen IV. Within the NOMAGE4 project a seminar on Generation IV Nuclear Energy Systems has been organized during 15-16th of October 2009. The aim of the seminar was to provide a forum for exchange of information, discussion on future research needs and networking of experts on Generation IV reactor concepts. As an outcome of the NOMAGE4, a few collaboration project proposals have been prepared/planned in 2009. The network was welcomed by the European Commission and was mentioned as an exemplary network with representatives from industries, universities, power companies and research institutes. NOMAGE4 has been invited to participate to the 'European Energy Research Alliance, EERA, workshop for nuclear structural materials' http://www.eera-set.eu/index.php?index=41 as external observers. Future plans include a new Nordic application for continuation of NOMAGE4 network. (author)

Nordic Nuclear Materials Forum for Generation IV Reactors

International Nuclear Information System (INIS)

Anghel, C.; Penttilae, S.

2010-03-01

A network for material issues for Generation IV nuclear power has been initiated within the Nordic countries. The objectives of the Generation IV Nordic Nuclear Materials Forum (NOMAGE4) are to put the basis of a sustainable forum for Gen IV issues, especially focussing on fuels, cladding, structural materials and coolant interaction. Other issues include reactor physics, dynamics and diagnostics, core and fuel design. The present report summarizes the work performed during the year 2009. The efforts made include identification of organisations involved in Gen IV issues in the Nordic countries, update of the forum website, http://www.studsvik.se/GenerationIV, and investigation of capabilities for research within the area of Gen IV. Within the NOMAGE4 project a seminar on Generation IV Nuclear Energy Systems has been organized during 15-16th of October 2009. The aim of the seminar was to provide a forum for exchange of information, discussion on future research needs and networking of experts on Generation IV reactor concepts. As an outcome of the NOMAGE4, a few collaboration project proposals have been prepared/planned in 2009. The network was welcomed by the European Commission and was mentioned as an exemplary network with representatives from industries, universities, power companies and research institutes. NOMAGE4 has been invited to participate to the 'European Energy Research Alliance, EERA, workshop for nuclear structural materials' http://www.eera-set.eu/index.php?index=41 as external observers. Future plans include a new Nordic application for continuation of NOMAGE4 network. (author)

Japanese authorities inform IAEA about accident at nuclear plant

International Nuclear Information System (INIS)

2004-01-01

Full text: The IAEA today received information from Japanese nuclear regulatory authorities about an accident in the steam generator turbine circuit of the Mihama Nuclear Power Plant (unit 3). According to the Japanese nuclear authorities this is a non-radioactive part of the plant. The regulatory body has reported that four contract employees died and 7 were injured, and stated that there was no release of radioactivity. The IAEA continues to be in contact with Japanese authorities and expects to receive updates on a continuous basis. No request for IAEA assistance has been received at this time. (IAEA)

Atomic scale modelling of materials of the nuclear fuel cycle

International Nuclear Information System (INIS)

Bertolus, M.

2011-10-01

This document written to obtain the French accreditation to supervise research presents the research I conducted at CEA Cadarache since 1999 on the atomic scale modelling of non-metallic materials involved in the nuclear fuel cycle: host materials for radionuclides from nuclear waste (apatites), fuel (in particular uranium dioxide) and ceramic cladding materials (silicon carbide). These are complex materials at the frontier of modelling capabilities since they contain heavy elements (rare earths or actinides), exhibit complex structures or chemical compositions and/or are subjected to irradiation effects: creation of point defects and fission products, amorphization. The objective of my studies is to bring further insight into the physics and chemistry of the elementary processes involved using atomic scale modelling and its coupling with higher scale models and experimental studies. This work is organised in two parts: on the one hand the development, adaptation and implementation of atomic scale modelling methods and validation of the approximations used; on the other hand the application of these methods to the investigation of nuclear materials under irradiation. This document contains a synthesis of the studies performed, orientations for future research, a detailed resume and a list of publications and communications. (author)

Radiation protection databases of nuclear safety regulatory authority

International Nuclear Information System (INIS)

Janzekovic, H.; Vokal, B.; Krizman, M.

2003-01-01

Radiation protection and nuclear safety of nuclear installations have a common objective, protection against ionising radiation. The operational safety of a nuclear power plant is evaluated using performance indicators as for instance collective radiation exposure, unit capability factor, unplanned capability loss factor, etc. As stated by WANO (World Association of Nuclear Operators) the performance indicators are 'a management tool so each operator can monitor its own performance and progress, set challenging goals for improvement and consistently compare performance with that of other plants or industry'. In order to make the analysis of the performance indicators feasible to an operator as well as to regulatory authorities a suitable database should be created based on the data related to a facility or facilities. Moreover, the international bodies found out that the comparison of radiation protection in nuclear facilities in different countries could be feasible only if the databases with well defined parameters are established. The article will briefly describe the development of international databases regarding radiation protection related to nuclear facilities. The issues related to the possible development of the efficient radiation protection control of a nuclear facility based on experience of the Slovenian Nuclear Safety Administration will be presented. (author)

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

International Nuclear Information System (INIS)

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

2016-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2016-10-15

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

Study of nuclear material accounting

International Nuclear Information System (INIS)

Ruderman, H.

1977-01-01

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

Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1993 ed

International Nuclear Information System (INIS)

1993-10-01

This is the fourth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM). The reporting format was established at consecutive meetings of SAGSTRAM, whose memberships consists of national competent authorities responsible for the transport of radioactive material from those Member States who have a nuclear industry and others who have shown a keen interest in the IAEA's transport safety programme. Through the PACKTRAM database, the Secretariat collects administrative and technical information on package approval certificates to assist national competent authorities in regulating radioactive material movements in their country. The database carries information on extant certificates and those that expired within the last two complete calendar years. The 1985 Edition of IAEA Safety Series No. 6, the 'Regulations for the Safe Transport of Radioactive Material'' highlights the role of competent authorities in assuring regulatory compliance in their own countries. Package approval certificates are an important aspect of that function. This document aims to be a useful reference for competent authorities as well as for manufacturers and shippers of radioactive material. 6 tabs

Directory of national competent authorities` approval certificates for package design, special form material and shipment of radioactive material. 1995 edition

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

This is the sixth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM). The reporting format was established at consecutive meetings of SAGSTRAM, whose membership consists of national competent authorities responsible for the transport of radioactive material from those Member States who have a nuclear industry and others who have shown a keen interest in the IAEA`s transport safety programme. Through the PACKTRAM database, the Secretariat collects administrative and technical information on package approval certificates to assist national competent authorities in regulating radioactive material movements in their country. The database carries information on extant certificates and those that expired within the last complete calendar year. The 1985 Edition of IAEA Safety Series No. 6, the ``Regulations for the Safe Transport of Radioactive Material`` highlights the role of competent authorities in assuring regulatory compliance in their own countries. Package approval certificates are an important aspect of that function. This document aims to be a useful reference for competent authorities as well as for manufacturers and shippers of radioactive material. 6 tabs.

Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1999 Edition

International Nuclear Information System (INIS)

1999-08-01

This is the tenth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Transport Safety Standards Advisory Committee (TRANSSAC), formerly known as the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM). The reporting format was established at consecutive meetings of SAGSTRAM and endorsed by TRANSSAC, whose membership consists of national competent authorities responsible for the transport of radioactive material from those Member States who have a nuclear industry and others who have shown a keen interest in the IAEA's transport safety programme. Through the PACKTRAM database, the Secretariat collects administrative and technical information on package approval certificates to assist national competent authorities in regulating radioactive material movements in their country. The database carries information on extant certificates and those that expired within the last complete calendar year. The 1985 Edition of IAEA Safety Series No. 6, the 'Regulations for the Safe Transport of Radioactive Material' highlights the role of competent authorities in assuring regulatory compliance in their own countries. Package approval certificates are an important aspect of that function. This document aims to be a useful reference for competent authorities as well as for manufacturers and shippers of radioactive material

Nuclear material control in Spain

International Nuclear Information System (INIS)

Velilla, A.

1988-01-01

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

Automated nuclear materials accounting

International Nuclear Information System (INIS)

Pacak, P.; Moravec, J.

1982-01-01

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

Basic fracture toughness requirements for ferritic materials of nuclear class pressure retaining equipment in NPP

International Nuclear Information System (INIS)

Ning Dong; Yao Weida

2005-01-01

In this paper, theory basis on cold brittleness and anti-brittle fracture design of ferritic materials are introduced summarily and fracture toughness requirements for ferritic materials in ASME code for nuclear safety class pressure retaining equipment in NPP are summarized and evaluated. The results show that notch impact toughness requirements for materials relate to nuclear safety class of materials so as to ensure that brittle fracture of retaining pressure boundary in NPP can not occur. (authors)

New materials in nuclear fusion reactors

International Nuclear Information System (INIS)

Iwata, Shuichi

1988-01-01

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

The control of vehicles used in transport of sensitive nuclear material

International Nuclear Information System (INIS)

Loiseau, O.; Larrignon, D.; Autrusson, B.

2010-01-01

Most sensitive nuclear materials are usually shipped in specific vehicles with a reinforced protection; such vehicles are generally escorted, tracked and watched over from a distant control centre. Among the various publications made by the IAEA in relation with the CPPNM, the INFCIRC/225 introduces major recommendations for physical protection of nuclear materials in general and particularly during transport. For instance, the text recommends - for the terrestrial shipment of most sensitive material - the use of vehicles specially designed to resist attack and equipped with a vehicle disabling device. Applying such a recommendation at a state level requires the intervention of a competent authority; the competent authority defines the framework of a validation process starting with the design of the vehicle and ending with the vehicle protection approval. The validation process needs articulating responsibilities between the three major actors who are: the operator in charge of the design, a technical support body in charge of technical evaluation, and the competent authority who is responsible for the final approval of the protection. This paper focuses on the approval process of reinforced protection vehicles in France; it aims at showing how such a process may contribute to the security of nuclear material shipments. The paper notably focuses on the responsibilities of the operators, the competent authority and the technical support organization. This approval process of the protection of a vehicle allows the authority to ensure that the protection setup is effective and operational in order to protect the cargo from a malicious threat. In such a process, the authority defines the threat and the objectives of protection; the authority may choose, in certain case, to recommend protection devices or solutions; the need for recommendation versus objective definition mostly depends on the environment of the vehicle and the constraints induced. The authority may

Guidance and considerations for the implementation of INFCIRC/225/Rev.4, the physical protection of nuclear material and nuclear facilities

International Nuclear Information System (INIS)

2000-05-01

This publication is intended to provide guidance and considerations for a State's competent authority to better understand and prescribe appropriate requirements, consistent with INFCIRC/225/Rev.4 for the protection of nuclear material and nuclear facilities which are compatible with accepted international practice. This report, together with a more detailed report, Handbook on the Physical Protection of Nuclear Material and Facilities, which addresses to the licencee or designer of physical protection systems who has specific implementation and compliance responsibilities, should be used in conjunction to each other to provide better and comprehensive guidance on physical protection

Guidance and considerations for the implementation of INFCIRC/225/Rev.4, the physical protection of nuclear material and nuclear facilities

International Nuclear Information System (INIS)

2002-05-01

This publication is intended to provide guidance and considerations for a State's competent authority to better understand and prescribe appropriate requirements, consistent with INFCIRC/225/Rev.4 for the protection of nuclear material and nuclear facilities which are compatible with accepted international practice. This report, together with a more detailed report, Handbook on the Physical Protection of Nuclear Material and Facilities, which addresses to the licensee or designer of physical protection systems who has specific implementation and compliance responsibilities, should be used in conjunction to each other to provide better and comprehensive guidance on physical protection

The physical protection of nuclear material and nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-06-01

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

The physical protection of nuclear material and nuclear facilities

International Nuclear Information System (INIS)

1999-06-01

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

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

International Nuclear Information System (INIS)

1978-03-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Byeon, Kee Hoh; Kim, Ho Dong; Song, Dae Yong; Ko, Won Il; Hong, Jong Sook; Lee, Byung Doo

1999-07-01

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.

Integrated Global Nuclear Materials Management Preliminary Concepts

International Nuclear Information System (INIS)

Jones, E; Dreicer, M.

2006-01-01

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

Materials and wastes from power generation of nuclear origin

International Nuclear Information System (INIS)

Dessus, Benjamin; Guillemette, Andre; Laponche, Bernard; Zerbib, Jean-Claude

2014-01-01

In most countries, spent nuclear fuel is directly stored in pools and constitute the bulk of highly radioactive waste. In France, reprocessing separates spent fuel into three categories: uranium, plutonium, minor actinides and fission products. Hence, a vast amount of very diverse radioactive materials are stored in various sites and conditions, under two denominations: 'nuclear materials' (which can be or are partly recycled) and 'radioactive waste' which should be permanently disposed of. The production of highly radioactive and long-lived waste raise legitimate questions on the use of nuclear energy for power production and many people think that it's a sufficient reason for giving up this technique. Concerning existing radioactive waste, the alternative to deep disposal should be: a) dry storage of spent fuel and other existing waste in protected sites (bunkers or hills), and b) more active research on the possibilities to reduce both radioactivity and the lifetime of radioactive waste. (authors)

Nuclear Materials: Reconsidering Wastes and Assets - 13193

Energy Technology Data Exchange (ETDEWEB)

Michalske, T.A. [Savannah River National Laboratory (United States)

2013-07-01

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

New safety and security requirements for the transport of nuclear and other radioactive materials in Hungary

International Nuclear Information System (INIS)

Katona, T.; Horvath, K.; Safar, J.

2016-01-01

In addition to the promulgation of mode-specific regulations of international transport of dangerous goods, some Hungarian governmental and ministerial decrees impose further conditions upon the transport of nuclear and other radioactive materials. One of these ministerial decrees on the transport, carriage and packaging of radioactive materials is under revision and it will require • approval of emergency response plan (including security and safety contingency plan); • report on transport incidents and accidents for classifying them in accordance with the INES scale; • the competent authority to request experts’ support for the approval of package designs, radioactive material designs and shipments. Regarding the security of the transport of nuclear and other radioactive materials a new Hungarian governmental decree and a related guidance are about to be published which will supply additional requirements in the field of the transport security especially concerning radioactive materials, implementing - among others - IAEA recommendations of the NSS No9 and No14. The main and relevant features of the Hungarian nuclear regulatory system and the details of both new decrees regarding the safety and security issues of transport of nuclear and other radioactive materials will be discussed. (author)

Bill project authorizing the approval of the amendment to the convention on physical protection of nuclear material - Nr 11

International Nuclear Information System (INIS)

Ayrault, Jean-Marc; Fabius, Laurent

2012-01-01

This document contains the brief text of the bill project and the text of the amendment to the Convention on physical protection of nuclear material which has been adopted in Vienna in August 2005 to amend the Convention adopted in October 1979. This amendment introduces the following measures: extension of the scope of application of the Convention to nuclear materials used for peaceful purposes, definition of the objectives of the Convention, articulation of the Convention with other international instruments, definition of the main principles of physical protection, strengthened international cooperation, legal issues concerning extradition and legal cooperation

Material degradation - a nuclear utility's view

International Nuclear Information System (INIS)

Spekkens, P.

2007-01-01

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

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

International Nuclear Information System (INIS)

Sembiring, D.

2001-01-01

. BAPETEN also established the Decree on the Guidance for Physical Protection of nuclear material under Chairman Decree of BAPETEN No. 02-P/1999 (adopted from IAEA document INFCIRC/225 Rev. 1), as the implementation of the Convention on Physical Protection of nuclear material signed in 1986 and ratified by Presidential Decree No. 49/86. The second component of the regulatory function is licensing. An organization or individual intending to utilized nuclear energy must obtain license from BAPETEN. Guidance for applicants is provided in the form of standard format, which contain license conditions. Any utilization of nuclear energy shall maintain physical protection program or security plans. When the applicants meet BAPETEN's criteria for physical protection of nuclear material and facility, a license is granted. By this licensing, BAPETEN is able to know where, by whom, and how the use of nuclear and radioactive materials is conducted. The third component of the regulatory function is inspection. To ensure that legal user's activities comply with BAPETEN regulation and the conditions of their licenses, BAPETEN periodically inspects BAPETEN-licensed facilities. Inspections can be announced or unannounced, and varies in scope and frequency according to the authorized activities. The finding of all inspection are documented in inspection reports. These reports are sent to the licensees to inform them of the BAPETEN findings. When inspections disclose violations of BAPETEN requirement, BAPETEN has a range of enforcement sanctions available. Recommendation stated in the inspection report requires the licensee to correct the problem, take steps to prevent a recurrence of the violation, and advise BAPETEN at the action it has taken. The result of inspection by BAPETEN is published periodically and open for public. Some illicit trafficking of nuclear and radioactive materials can be detected during inspections. This detection must lead to prompt information of BAPETEN in order to

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

International Nuclear Information System (INIS)

Kulinich, O.

2001-01-01

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

Nuclear material control in Brazil

International Nuclear Information System (INIS)

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

1988-01-01

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

Strategies and technologies for nuclear materials stewardship

International Nuclear Information System (INIS)

Cunningham, P.T.; Arthur, E.D.; Wagner, R.L. Jr.; Hanson, E.M.

1997-01-01

A strategy for future nuclear materials management and utilization from proliferation and long-term waste perspectives is described. It is aimed at providing flexible and robust responses to foreseeable nuclear energy scenarios. The strategy also provides for a smooth transition, in terms of technology development and facility implementation, to possible future use of breeder reactor technology. The strategy incorporates features that include minimization of stocks of separated plutonium; creation of a network of secure interim, retrievable storage facilities; and development and implementation of a system of Integrated Actinide Conversion Systems (IACS) aimed at near and far-term management of plutonium and other actinides. Technologies applicable to such IACS concepts are discussed as well as a high-level approach for implementation. (author)

ASNC upgrade for nuclear material accountancy of ACPF

Science.gov (United States)

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

2018-02-01

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

Uranium as Raw Material for Nuclear Energy

International Nuclear Information System (INIS)

Lelek, V.

2006-01-01

There is lot of information bringing our attention to the problem of limited raw material resources. Fortunately uranium for nuclear energy is very concentrated source and that is why its transport brings no problems and could be realized from anywhere. Second question is if overall resources are available for current nuclear energy development. Data documenting reasons for nowadays price growth are presenting and it is clearly shown that the most probable explanation is that there is gap in new uranium mines preparation and the lot of smaller mines were closed in the period of low uranium prices. Conclusion is that there is at least for the first half of this century even for thermal reactors enough uranium. Situation could be changed if there will massive production of liquid fuel using hydrogen, produced through nuclear heating. Public information about former military uranium resources are also included. Contemporary about one half of US nuclear power-stations is using high enriched uranium diluted with natural uranium - it is expected to continue this way up to 2012. Uranium is complicated market (Authors)

A method for assay of special nuclear material in high level liquid waste streams

International Nuclear Information System (INIS)

Venkata Subramani, C.R.; Swaminathan, K.; Asuvathraman, R.; Kutty, K.V.G.

2003-01-01

The assay of special nuclear material in the high level liquid waste streams assumes importance as this is the first stage in the extraction cycle and considerable losses of plutonium could occur here. This stream contains all the fission products as also the minor actinides and hence normal nuclear techniques cannot be used without prior separation of the special nuclear material. This paper presents the preliminary results carried out using wavelength dispersive x-ray fluorescence as part of the developmental efforts to assay SNM in these streams by instrumental techniques. (author)

Radiation Effects in Nuclear Waste Materials

International Nuclear Information System (INIS)

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

2003-01-01

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

Radiation Effects in Nuclear Waste Materials

International Nuclear Information System (INIS)

Weber, William J.

2005-01-01

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

Application of Regulation for recycling metals arising from Decommissioning of an Italian Nuclear Facility - Application of national regulations for metallic materials' recycling from the decommissioning of an Italian nuclear facility

International Nuclear Information System (INIS)

Varasano, Giovanni; Baldassarre, Leonardo; Petagna, Edoardo

2014-01-01

The start of the decommissioning of nuclear Italian sites requires proper management of clearance for large volumes of metallic materials. This paper describes the current legal framework relating to the Italian regulatory system of reference for the verification of the conditions of unconditional release of materials from nuclear installations, with particular reference to the recycling of metals. The definition of clearance levels, whether general or specific, ensures the clearance of materials arising from nuclear sites without further examinations. The Italian legislation on radiation protection requires that the removal of materials from authorized practices be subject to special requirements included in the authorization provisions. These requirements provide clearance levels that take account of the recommendations and technical guidelines supplied by the European Commission. The regulatory framework requires compliance with current technical and managerial requirements, issued by the National Regulatory Authority and annexed to the Ministerial Authorization, in which are shown the levels of surface activity and specific activity established for the unconditional release of metals from nuclear sites. The real challenge for the nuclear operator is the management of large amounts of waste materials arising from decommissioning activities. For the Italian operator SOGIN SpA is of extreme importance the correct application of national regulatory framework, in order to allow the most effective reduction of the amount of radioactive waste during decommissioning activities. (authors)

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

International Nuclear Information System (INIS)

2015-01-01

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

A review of tsp as one of the transportation security aspects of nuclear materials

International Nuclear Information System (INIS)

Wiryono

2013-01-01

A review has done for the Transportation Safety Plan (TSP) as one of the aspects of safety in the transport of nuclear materials. The review is necessary to harmonize national regulations with international practice. International practice of using TSP as one of the security requirements in addition to the Radiation Protection Program as a requirement of safety in the transport of nuclear materials. TSP is intended to ensure sound implementation of the transport of nuclear materials. TSP evaluation process can be done with a prescriptive approach, performance, and combinations. TSP contains information about administrative requirements, delivery security and response planning. TSP can be used to ensure the security of the implementation of the transport of nuclear materials effectively and efficiently. BAPETEN should require the applicant to submit the TSP as one document security requirements prior approval transporting nuclear materials. BAPETEN need to define the approach to the formulation and evaluation of TSP. BAPETEN need to set up an evaluation and inspection procedures for the implementation of TSP. (author)

Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1996 edition

International Nuclear Information System (INIS)

1996-09-01

This is the seventh annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificated (PACKTRAM) at the recommendation of the then Standing Advisory Group on the Sate Transport of Radioactive Material (SAGSTRAM). The functions of SAGSTRAM were taken over in 1996 by the Transport Safety Standards Advisory Committee (TRANSSAC). The reporting format was established at consecutive meetings of SAGSTRAM, whose membership consists of national competent authorities responsible for the transport of radioactive material from those Member States who have a nuclear industry and others who have shown a keen interest in the IAEA's transport safety programme. Through the PACKTRAM database, the Secretariat collects administrative and technical information on package approval certificates to assist national competent authorities in regulating radioactive material movements in their country. The database carries information on extant certificates and those that expired within the last complete calendar year. The 1985 Edition of IAEA Safety Series No. 6, the ''Regulations for the Safe Transport of Radioactive Material'', highlights the role of competent authorities in assuring regulatory compliance in their own countries. Package approval certificates are an important aspect of that function. This document aims to be a useful reference for competent authorities as well as for manufacturers and shippers of radioactive material. 6 tabs

Analysis of nuclear material flow for experimental DUPIC fuel fabrication process at DFDF

International Nuclear Information System (INIS)

Lee, H. H.; Park, J. J.; Shin, J. M.; Lee, J. W.; Yang, M. S.; Baik, S. Y.; Lee, E. P.

1999-08-01

This report describes facilities necessary for manufacturing experiment for DUPIC fuel, manufacturing process and equipment. Nuclear material flows among facilities, in PIEF and IMEF, for irradiation test, for post examination of DUPIC fuel, for quality control, for chemical analysis and for treatment of radioactive waste have been analyzed in details. This may be helpful for DUPIC project participants and facility engineers working in related facilities to understand overall flow for nuclear material and radioactive waste. (Author). 14 refs., 15 tabs., 41 figs

Analysis of nuclear material flow for experimental DUPIC fuel fabrication process at DFDF

Energy Technology Data Exchange (ETDEWEB)

Lee, H. H.; Park, J. J.; Shin, J. M.; Lee, J. W.; Yang, M. S.; Baik, S. Y.; Lee, E. P

1999-08-01

This report describes facilities necessary for manufacturing experiment for DUPIC fuel, manufacturing process and equipment. Nuclear material flows among facilities, in PIEF and IMEF, for irradiation test, for post examination of DUPIC fuel, for quality control, for chemical analysis and for treatment of radioactive waste have been analyzed in details. This may be helpful for DUPIC project participants and facility engineers working in related facilities to understand overall flow for nuclear material and radioactive waste. (Author). 14 refs., 15 tabs., 41 figs.

International dimension of illicit trafficking in nuclear and other radioactive material

International Nuclear Information System (INIS)

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

2002-01-01

of nuclear material and radiation sources have been reported in many other countries. For example, uranium enriched to 19.9 percent was stolen from the Kinshasa research reactor in the Congo in mid-1990's. Part of the material was seized from an Italian smuggling network in 1998 and the rest remains missing. Uranium concentrate stolen from Indian uranium mines was seized in India on several occasions, some of it destined for Pakistan: Multiple thefts of ionizing radiation sources have been recorded in the United States. Another problem facing many countries is the illegal transport of contaminated scrap metal or radioactive waste. Russian customs official have been complaining about multiple illegal shipments of radioactive waste from China stopped at the Russian border. This paper will provide results of the analysis of the DSTO database and recommendations for strengthening international cooperation aimed at preventing illicit trafficking of nuclear and other radioactive material an a global scale. (author)

A database for transmutation of nuclear materials on internet

Energy Technology Data Exchange (ETDEWEB)

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

1998-03-01

A database system on Internet for nuclear material design and selection used in various reactors are developed in NRIM site of `Data-Free-Way`. 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 nuclides and radioactivity in a material can be easily retrieved though the evaluation is qualitatively. (author)

Characterization of semiconductor and frontier materials by nuclear microprobe technology

International Nuclear Information System (INIS)

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

2002-01-01

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

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.

Virtual private networks application in Nuclear Regulatory Authority of Argentina

International Nuclear Information System (INIS)

Glidewell, Donnie D.; Smartt, Heidi A.; Caskey, Susan A.; Bonino, Anibal D.; Perez, Adrian C.; Pardo, German R.; Vigile, Rodolfo S.; Krimer, Mario

2004-01-01

As the result of the existence of several regional delegations all over the country, a requirement was made to conform a secure data interchange structure. This would make possible the interconnection of these facilities and their communication with the Autoridad Regulatoria Nuclear (ARN) headquarters. The records these parts exchange are often of classified nature, including sensitive data by the local safeguards inspectors. On the other hand, the establishment of this network should simplify the access of authorized nuclear and radioactive materials users to the ARN databases, from remote sites and with significant trust levels. These requirements called for a network that should be not only private but also secure, providing data centralization and integrity assurance with a strict user control. The first proposal was to implement a point to point link between the installations. This proposal was deemed as economically not viable, and it had the disadvantage of not being easily reconfigurable. The availability of new technologies, and the accomplishment of the Action Sheet 11 under an agreement between Argentine Nuclear Regulatory Authority and the United States Department of Energy (DOE), opened a new path towards the resolution of this problem. By application of updated tunneling security protocols it was possible to project a manageable and secure network through the use of Virtual Private Networking (VPN) hardware. A first trial installation of this technology was implemented between ARN headquarters at Buenos Aires and the Southern Region Office at Bariloche, Argentina. This private net is at the moment under test, and it is planned to expand to more sites in this country, reaching for example to nuclear power plants. The Bariloche installation had some interesting peculiarities. The solutions proposed to them revealed to be very useful during the development of the network expansion plans, as they showed how to adapt the VPN technical requisites to the

Radiation resistance of cable insulation and jacket materials for nuclear power plants

International Nuclear Information System (INIS)

Morita, Minoru; Kon, Shuji; Nishikawa, Ichiro

1978-01-01

The cables for use in nuclear power plants are required to satisfy the specific environmental resistance and excellent flame resistance as stipulated in IEEE Std. 383. The materials to be used to cables intended for this specific purpose of use must therefore be strictly tested so as to evaluate their flame resistance in addition to compliance with various environmental requirements, such as heat resistance, water-vapor resistance, and radiation resistance. This paper describes general information on radiation resistance and deterioration of various high-molecular materials, suggests the direction of efforts to be made to improve their properties including flame resistance of various rubber and plastic materials for cables to be used in nuclear power plants, and indicates the performance characteristics of such materials. (author)

Some ideas for next-generation controlled nuclear materials accountability techniques

International Nuclear Information System (INIS)

Brough, W.; Parrish, C.

1994-08-01

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

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

International Nuclear Information System (INIS)

2015-01-01

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

Introduction to nuclear material safeguards

International Nuclear Information System (INIS)

Kuroi, Hideo

1986-01-01

This article is aimed at outlining the nuclear material safeguards. The International Atomic Energy Agency (IAEA) was established in 1957 and safeguards inspection was started in 1962. It is stressed that any damage resulting from nuclear proliferation would be triggered by a human intentional act. Various measures have been taken by international societies and nations, of which the safeguards are the only means which relay mainly on technical procedures. There are two modes of diversing nuclear materials to military purposes. One would be done by national intension while the other by indivisulas or expert groups, i.e., sub-national intention. IAEA is responsible for the prevention of diversification by nations, for which the international safeguards are being used. Measures against the latter mode of diversification are called nuclear protection, for which each nation is responsible. The aim of the safeguards under the Nonproliferation Treaty is to detect the diversification of a significant amount of nuclear materials from non-military purposes to production of nuclear explosion devices such as atomic weapons or to unidentified uses. Major technical methods used for the safeguards include various destructive and non-destructive tests as well as containment and monitoring techniques. System techniques are to be employed for automatic containment and monitoring procedures. Appropriate nuclear protection system techniques should also be developed. (Nogami, K.)

Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1997 Edition

International Nuclear Information System (INIS)

1997-08-01

This is the eighth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the then Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM). The functions of SAGSTRAM were taken over in 1996 by the Transport Safety Standards Advisory Committee (TRANSSAC). The reporting format was established at consecutive meetings of SAGSTRAM, whose membership consisted of national competent authorities responsible for the transport of radioactive material from those Member States who have a nuclear industry and others who showed a keen interest in the IAEA's transport safety programme. TRANSSAC underscores the importance of data collecting activities and recommends the continued publication of this annual report. The 1985 Edition of Safety Series No. 6, the ''Regulations for the Safe Transport of Radioactive Material'', highlights the role of competent authorities in assuring regulatory compliance in their own countries. The issuance of package approval certificates is an important aspects of that function. This document aims to be a useful reference for competent authorities as well as for manufacturers and shippers of radioactive material. 6 tabs

The century of nuclear materials

Science.gov (United States)

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

2018-03-01

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

National practices in physical protection of nuclear materials. Regulatory basis

International Nuclear Information System (INIS)

Goltsov, V.Y.

2002-01-01

criminal code of Russian Federation regarding improper execution of duties on and theft of nuclear materials and equipment that could be used for weapons of mass destruction construction. Minatom of Russia is actively elaborating ministerial documents on physical protection. Since 1995 till 2001 there were developed and put in force 21 this topic related documents including the following: physical protection terminology; general approaches to physical protection ensuring; vulnerability analysis of nuclear-hazardous facilities; physical protection systems designing; organizing of safeguards and security services at nuclear-hazardous facilities; operation of automated physical protection systems; communication and data exchange in physical protection systems; certification of technical means of physical protection; physical protection system information protection; ministerial on-site guarding of nuclear-hazardous facilities; provision of ministerial control of physical protection condition; interaction of different entities participating physical protection at ministerial level. (author)

The Physical Protection of Nuclear Material

International Nuclear Information System (INIS)

1993-09-01

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

The Physical Protection of Nuclear Material

International Nuclear Information System (INIS)

1993-09-01

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

The Physical Protection of Nuclear Material

International Nuclear Information System (INIS)

1993-01-01

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

The Physical Protection of Nuclear Material

International Nuclear Information System (INIS)

1993-09-01

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

Metabonomics for detection of nuclear materials processing

International Nuclear Information System (INIS)

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

2010-01-01

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

Nuclear materials facility safety initiative

International Nuclear Information System (INIS)

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

2000-01-01

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

Modernizing computerized nuclear material accounting systems

International Nuclear Information System (INIS)

Erkkila, B.H.; Claborn, J.

1995-01-01

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

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

International Nuclear Information System (INIS)