The international fusion materials irradiation facility

International Nuclear Information System (INIS)

Shannon, T.E.; Cozzani, F.; Crandall, D.H.; Wiffen, F.W.; Katsuta, H.; Kondo, T.; Teplyakov, V.; Zavialsky, L.

1994-01-01

It is widely agreed that the development of materials for fusion systems requires a high flux, 14 MeV neutron source. The European Union, Japan, Russia and the US have initiated the conceptual design of such a facility. This activity, under the International Energy Agency (IEA) Fusion Materials Agreement, will develop the design for an accelerator-based D-Li system. The first organizational meeting was held in June 1994. This paper describes the system to be studied and the approach to be followed to complete the conceptual design by early 1997

Proceedings of the 3rd international symposium on material chemistry in nuclear environment (MATERIAL CHEMISTRY '02)

International Nuclear Information System (INIS)

2003-03-01

The volume contains all presented papers during the 3rd International Symposium on Material Chemistry in Nuclear Environment: MATERIAL CHEMISTRY 02 (MC'02), held March 13-15, 2002. The purpose of this symposium is to provide an international forum for the discussion of recent progress in the field of materials chemistry in nuclear environments. This symposium intends to build on the success of the previous symposiums held in Tsukuba in 1992 and 1996. The topics discussed in the symposium MC'02 are Chemical Reaction and Thermodynamics, Degradation Phenomena, New Characterization Technology, Fabrication and New Materials, Composite Materials, Surface Modification, and Computational Science. The 61 of the presented papers are indexed individually. (J.P.N.)

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.)

The regulations concerning the uses of international controlled material

International Nuclear Information System (INIS)

1979-01-01

The regulations are defined under the law for the regulations of nuclear source materials, nuclear fuel materials and reactors and provisions concerning the uses of international controlled material in the order for execution of the law. Basic concepts and terms are explained, such as: area of material delivery; fluctuation of stock; batch; real stock, effective value; fuel assembly and main measuring point. The application for permission of the uses of international controlled material shall be filed to the Director General of Science and Technology Agency by the processor, the establisher of reactor, the reprocessor or the user for each works or enterprise, listing name and address of the person, name and location of the works or the enterprise where such material is used, kind and quantity of the material and expected period of the uses. Records shall be made and kept for particular periods for each works or enterprise on specified matters, including especially delivery, stock and fluctuation of stock of nuclear source or fuel material, etc. Provisions on control of measurement, method of analysis and information processing business are stipulated. Reports shall be submitted to the Director in the forms attached on delivery, control and fluctuation of stock of nuclear source or fuel material, etc. (Okada, K.)

Proceedings of the international workshop on spallation materials technology

Energy Technology Data Exchange (ETDEWEB)

Mansur, L.K.; Ullmaier, H. [comps.

1996-10-01

This document contains papers which were presented at the International Workshop on Spallation Materials Technology. Topics included: overviews and thermal response; operational experience; materials experience; target station and component design; particle transport and damage calculations; neutron sources; and compatibility.

Proceedings of the international workshop on spallation materials technology

International Nuclear Information System (INIS)

Mansur, L.K.; Ullmaier, H.

1996-01-01

This document contains papers which were presented at the International Workshop on Spallation Materials Technology. Topics included: overviews and thermal response; operational experience; materials experience; target station and component design; particle transport and damage calculations; neutron sources; and compatibility

Abstracts of International Conference on Sol-Gel Materials' 04

International Nuclear Information System (INIS)

2004-01-01

International Conference on Sol-Gel Materials '04 was an important forum for discussion on problems related to sol-gel processes applied for preparation materials with special physical properties and assignment. The application of sol-gel materials as phosphors, surface coatings, sensors, waveguides, medical implants, joints etc. has been presented. Preparation conditions, methods of physical characterization as well as optimal chemical composition of such materials have been also discussed in detail

IFMIF : International Fusion Materials Irradiation Facility Conceptual Design Activity: Final report

International Nuclear Information System (INIS)

Martone, M.

1997-01-01

This report documents the results of the Conceptual Design Activity (CDA) on the International Fusion Materials Irradiation Facility (IFMIF), conducted during 1995 and 1996. The activity is under the auspices of the International Energy Agency (IEA) Implementing Agreement for a Programme of Research and Development on Fusion Materials. An IEA Fusion Materials Executive Subcommittee was charged with overseeing the IFMIF-CDA work. Participants in the CDA are the European Union, Japan, and the United States, with the Russian Federation as an associate member

IFMIF : International Fusion Materials Irradiation Facility Conceptual Design Activity: Final report

Energy Technology Data Exchange (ETDEWEB)

Martone, M [ENEA, Centro Ricerche Frascati, Rome (Italy)

1997-01-01

This report documents the results of the Conceptual Design Activity (CDA) on the International Fusion Materials Irradiation Facility (IFMIF), conducted during 1995 and 1996. The activity is under the auspices of the International Energy Agency (IEA) Implementing Agreement for a Programme of Research and Development on Fusion Materials. An IEA Fusion Materials Executive Subcommittee was charged with overseeing the IFMIF-CDA work. Participants in the CDA are the European Union, Japan, and the United States, with the Russian Federation as an associate member.

Assessment of international reference materials for isotope-ratio analysis (IUPAC Technical Report)

Science.gov (United States)

Brand, Willi A.; Coplen, Tyler B.; Vogl, Jochen; Rosner, Martin; Prohaska, Thomas

2014-01-01

Since the early 1950s, the number of international measurement standards for anchoring stable isotope delta scales has mushroomed from 3 to more than 30, expanding to more than 25 chemical elements. With the development of new instrumentation, along with new and improved measurement procedures for studying naturally occurring isotopic abundance variations in natural and technical samples, the number of internationally distributed, secondary isotopic reference materials with a specified delta value has blossomed in the last six decades to more than 150 materials. More than half of these isotopic reference materials were produced for isotope-delta measurements of seven elements: H, Li, B, C, N, O, and S. The number of isotopic reference materials for other, heavier elements has grown considerably over the last decade. Nevertheless, even primary international measurement standards for isotope-delta measurements are still needed for some elements, including Mg, Fe, Te, Sb, Mo, and Ge. It is recommended that authors publish the delta values of internationally distributed, secondary isotopic reference materials that were used for anchoring their measurement results to the respective primary stable isotope scale.

IFMIF : International Fusion Materials Irradiation Facility Conceptual Design Activity: Executive summary

International Nuclear Information System (INIS)

1997-01-01

This report is a summary of the results of the Conceptual Design Activity (CDA) on the International Fusion Materials Irradiation Facility (IFMIF), conducted during 1995 and 1996. The activity is under the auspices of the International Energy Agency (IEA) Implementing Agreement for a Programme of Research and Development on Fusion Materials. An IEA Fusion Materials Executive Subcommittee was charged with overseeing the IFMIF-CDA work. Participants in the CDA are the European Union, Japan, and the United States, with the Russian Federation as an associate member

IFMIF : International Fusion Materials Irradiation Facility Conceptual Design Activity: Executive summary

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-01-01

This report is a summary of the results of the Conceptual Design Activity (CDA) on the International Fusion Materials Irradiation Facility (IFMIF), conducted during 1995 and 1996. The activity is under the auspices of the International Energy Agency (IEA) Implementing Agreement for a Programme of Research and Development on Fusion Materials. An IEA Fusion Materials Executive Subcommittee was charged with overseeing the IFMIF-CDA work. Participants in the CDA are the European Union, Japan, and the United States, with the Russian Federation as an associate member.

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.

75 FR 38168 - Hazardous Materials: International Regulations for the Safe Transport of Radioactive Material (TS...

Science.gov (United States)

2010-07-01

... may also provide contact information, such as a telephone number and/or e-mail address. PHMSA and the.... PHMSA-2010-0130 (Notice No.10-2)] Hazardous Materials: International Regulations for the Safe Transport... (IAEA) ``Regulations for the Safe Transport of Radioactive Material'' (TS-R-1), which is scheduled for...

Management of Global Nuclear Materials for International Security

International Nuclear Information System (INIS)

Isaacs, T; Choi, J-S

2003-01-01

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

The potential value of dynamic materials control in international safeguards

International Nuclear Information System (INIS)

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

1979-01-01

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

Liability and insurance aspects of international transport of nuclear materials

International Nuclear Information System (INIS)

van Gijn, S.H.

1985-01-01

The Paris and Vienna Conventions do not affect the application of any international transport agreement already in force. However, in certain circumstances both the nuclear operator and the carrier may be held liable for nuclear damage which arises during international transports of nuclear materials. The ensuing cumulation of liabilities under the Nuclear and Transport Conventions may cause serious problems in obtaining adequate insurance cover for such transports. The 1971 Brussels Convention seeks to solve this problem by exonerating any person who might be held liable for nuclear damage under an international maritime convention or national law. Similar difficulties are encountered in the case of transports of nuclear materials between states which have and states which have not ratified the Paris and Vienna Conventions. (NEA) [fr

Materials management in an internationally safeguarded fuels reprocessing plant

International Nuclear Information System (INIS)

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

1980-04-01

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

Materials management in an internationally safeguarded fuels reprocessing plant

Energy Technology Data Exchange (ETDEWEB)

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

1980-04-01

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

Proceedings of DAE-BRNS third international symposium on materials chemistry

International Nuclear Information System (INIS)

Tyagi, Deepak; Banerjee, Atindra Mohan; Nigam, Sandeep; Varma, Salil; Tripathi, Arvind Kumar; Bharadwaj, Shyamala Rajkumar; Das, Dasarathi

2010-12-01

The present volume consists of the proceedings of the DAE-BRNS Third International Symposium on Materials Chemistry. In order to keep pace with the advancements made in the area of materials chemistry, new topics like materials for energy conversion, biomaterials, carbon based materials, soft condensed materials, thin films, surface chemistry, polymer based materials, organic and organometallics, magnetic materials and high purity materials have been included in this symposium while topics like nuclear materials, nanomaterials and clusters, catalysis, chemical sensors, fuel cell materials and computational research in materials chemistry have been continued as important features of the symposium. Papers relevant to INIS are indexed separately

The regulations concerning the uses of international controlled materials

International Nuclear Information System (INIS)

1981-01-01

This rule is established under the provisions of the law concerning the regulation of nuclear raw materials, nuclear fuel materials and nuclear reactors and the ordinance for the execution of this law and to enforce them. Basic terms are defined, such as material delivery and receipt area, stock fluctuation, batch, real inventory, effective value, fuel assembly and main measuring point. The application for the permission of using internationally regulated goods shall list the kinds of the goods classifying into materials and facilities for each partner country of international agreements concerning these goods. When such goods are utilized by fabricators, persons who install reactors, reprocessors or users, they shall file application to the Director General of the Science and Technology Agency for each works or enterprise where these goods are employed. The application shall include names and addresses, the names and places of works or enterprises where the goods are used, the kinds and quantities of the goods and expected period of usage etc. Records shall be made on the items specified for refiners, fabricators, persons who install reactors and users, respectively, and kept for particular periods. Measurement control, analysis method and business rules are defined. Reports shall be submitted to the Director General on the receipt and delivery, control, and stock fluctuation of nuclear raw materials and fuel materials, etc. (Okada, K.)

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.)

International measures needed to protect metal recycling facilities from radioactive materials

International Nuclear Information System (INIS)

Mattia, M.; Wiener, R.

1999-01-01

In almost every major city and region of every country, there is a recycling facility that is designed to process or consume scrap metal. These same countries will probably have widespread applications of radioactive materials and radiation generating equipment. This material and equipment will have metal as a primary component of its housing or instrumentation. It is this metal that will cause these sources of radioactivity, when lost, stolen or mishandled, to be taken to a metal recycling facility to be sold for the value of the metal. This is the problem that has faced scrap recycling facilities for many years. The recycling industry has spent millions of dollars for installation of radiation monitors and training in identification of radioactive material. It has expended millions more for the disposal of radioactive material that has mistakenly entered these facilities. Action must be taken to prevent this material from entering the conventional recycling process. There are more than 2,300 known incidents of radioactive material found in recycled metal scrap. Worldwide, more than 50 smeltings of radioactive sources have been confirmed. Seven fatal accidents involving uncontrolled radioactive material have also been documented. Hazardous exposures to radioactive material have plagued not just the workers at metal recycling facilities. The families of these workers, including their children, have been exposed to potentially harmful levels of radioactivity. The threat from this material does not stop there. Radioactive material that is not caught at recycling facilities can be melted and the radioactivity has been found in construction materials used to build homes, as well as shovels, fencing material, and furniture offered for sale to the general public. The time has come for the international community to address the issue of the uncontrolled sources of radioactive material. The following are the key points that must be addressed. (i) Identification of sources

ITER at the international conference on fusion reactor materials

International Nuclear Information System (INIS)

Kalinin, G.; Barabash, V.; Matera, R.

1998-01-01

The reports summarizes the topics of the eighth International Conference on Fusion Reactor Materials (ICFRM-8) which was held in Sendai, Japan, on 26-31 October 1997. The ICFRM is focused on the whole spectrum of materials and technologies to be applied in fusion reactors and related facilities. The total number of conference participants was over 500, representing 24 countries and about 600 oral and poster papers were presented at the conference. Three sessions were devoted to ITER materials: (i) Design-Materials Interface and ITER (oral session); (ii) ITER, Irradiation Facility and Technology, (poster session); (iii) ITER and Beyond (discussion session)

PREFACE: 1st International Conference on Rheology and Modeling of Materials

Science.gov (United States)

Gömze, László A.

2015-04-01

Understanding the rheological properties of materials and their rheological behaviors during their manufacturing processes and in their applications in many cases can help to increase the efficiency and competitiveness not only of the finished goods and products but the organizations and societies also. The more scientific supported and prepared organizations develop more competitive products with better thermal, mechanical, physical, chemical and biological properties and the leading companies apply more competitive knowledge, materials, equipment and technology processes. The idea to organize in Hungary the 1st International Conference on Rheology and Modeling of Materials we have received from prospective scientists, physicists, chemists, mathematicians and engineers from Asia, Europe, North and South America including India, Korea, Russia, Turkey, Estonia, France, Italy, United Kingdom, Chile, Mexico and USA. The goals of ic-rmm1 the 1st International Conference on Rheology and Modeling of Materials are the following: • Promote new methods and results of scientific research in the fields of modeling and measurements of rheological properties and behavior of materials under processing and applications. • Change information between the theoretical and applied sciences as well as technical and technological implantations. • Promote the communication between the scientists of different disciplines, nations, countries and continents. The international conference ic-rmm1 provides a platform among the leading international scientists, researchers, PhD students and engineers for discussing recent achievements in measurement, modeling and application of rheology in materials technology and materials science of liquids, melts, solids, crystals and amorphous structures. Among the major fields of interest are the influences of material structures, mechanical stresses temperature and deformation speeds on rheological and physical properties, phase transformation of

International Conference on Materials, Processing and Product Engineering 2015 (MPPE2015)

International Nuclear Information System (INIS)

Eck, S; Ebner, R; Ludwig, A

2016-01-01

The Materials Center Leoben Forschung GmbH (MCL) and the Austrian Society for Metallurgy and Materials (ASMET) have jointly organized the 'First International Conference on Materials, Processing and Product Engineering - MPPE' held in the Congress Center of Leoben from Nov. 3 rd to 5 th , 2015. The main topic of the conference was to present the state of the art in fundamental knowledge and technological expertise enabling and stimulating the development of knowledge based innovations across the entire product value chain starting from the material synthesis, proceeding with the processing of products and concluding with their in-service behaviour until the end of the product life time. Hence, the International Conference on Materials, Processing and Product Engineering MPPE 2015 focused on the core regions of industrial production chains, covering topics such as • Development and characterization of materials; • Materials synthesis and processing; • Dimensioning of components including integrated materials and process modelling; • Behaviour of materials and components during service. The scientific and technological goal was to present the state of the art of theoretical, experimental and numerical techniques and their combinations that are capable of improving the competitiveness of modern production facilities. (paper)

PREFACE: MRS International Materials Research Conference (IMRC-2008)

Science.gov (United States)

Wang, Zhanguo; Qiu, Yong; Li, Yongxiang

2009-03-01

This volume contains selected papers presented at the MRS International Materials Research Conference (IMRC-2008) held in Chongqing, China, 9-12 June 2008. IMRC-2008 included 9 symposia of A. Eco/Environmental Materials, B. Sustainable Energy Materials, C. Electronic Packaging Materials, D. Electronic Materials, E. Materials and Processes for Flat-panel Displays, F. Functional Ceramics, G. Transportation Materials, H. Magnesium and I. Biomaterials for Medical Applications. Nearly 1200 participants from 33 countries attended the conference, and the conference organizers received more than 700 papers. After the peer review processes, 555 papers were selected to be published in 9 Journals or proceedings, including J. of Materials Research (JMR), Rare Metal Materials and Engineering, J. of Univ. Science and Technology Beijing, Biomedical Materials: Materials for Tissue Engineering and Regenerative Medicine, Chinese Journal of Aeronautics, Materials Science Forum, and Journal of Physics: Conference Series. Among the 555 selected papers, 91 papers are published in this volume, and the topics mainly cover electronic matrials, processes for flat-panel displays and functional ceramics. The editors would like to give special thanks to the graduate students Liwu Jiang, Ming Li and Di He from Beihang University for their hard work compiling and typesetting each paper in this volume. Zhanguo Wang, Yong Qiu and Yongxiang Li Editors

INTRAW, the EU Observatory for raw materials: fostering international cooperation and developing new opportunities

Science.gov (United States)

Correia, Victor; Allington, Ruth; Keane, Christopher

2016-04-01

A secure supply of raw materials is a European priority that extends beyond country borders and national policies. Recent European initiatives have pioneered the development of an EU strategy on raw materials emphasizing the concept of the "added value chain", which continues to pursue the three pillar strategy to: (1) ensure the fair and sustainable supply of raw materials from international markets, promoting international cooperation with developed and developing countries; (2) foster sustainable supply of raw materials from European sources, and (3) reduce consumption of primary raw materials by increasing resource efficiency and promoting recycling. This contribution presents the Horizon 2020 funded project INTRAW, the objective of which is to establish the European Union's International Observatory for Raw Materials. The creation and maintenance of the European Union's International Observatory for Raw Materials is designed to have a strong impact in two dimensions: 1. To narrow the existing gap in aspects of the raw materials knowledge infrastructure in the EU by providing a link with the same knowledge infrastructure in technologically advanced reference countries. This should contribute to the harmonization of mineral policies all over the EU, by providing data that enables evidence-based policies and appropriate, cost-effective management, planning and adaptation decisions by the public sector. This will benefit businesses, industry and society. The Observatory will also provide to policy makers in the EU and its Member States the data they need to facilitate discussion in multilateral forums. 2. To enable a better alignment of the R&I activities among the individual EU members and international cooperation countries AND between the European Union and international cooperation countries by boosting synergies with international research and innovation programmes. This way the EU's role and scientific capabilities in the raw materials area will be

Evaluation of internal/external exposure from interior building materials

International Nuclear Information System (INIS)

Furuta, Etsuko; Morita-Murase, Yuko; Yoshizawa, Yukio

2008-01-01

Internal exposure to alpha particles emitted from 222 Rn (radon) and its daughters is the second leading cause of lung cancer. As a source of indoor radon in home, there are interior building materials that contain radioactive minerals. These radioactive consumer products have been claimed by distributors to have effect of 'minus-ion' or 'radon spring' for healthy promotion. We analyzed radioactive nuclides contained in the interior building materials, and measured radon levels released from them. The results of gamma-ray spectrometry revealed that these interior building materials contain U- and Th-series nuclides. The densities of some radioactive nuclides in the tile used for a bathroom exceeded the exempt limits of International Basic Safety Standards. However, the radon densities released from the tile was lower than detectable limit. In contrast, one of the wallpaper released 34 Bq·m -3 of radon gas in a 50-liter container. This value is two times higher than the average radon level in Japanese homes. The minus-ion effect' wallpapers are thought to be a cause of residential exposure to radon. (author)

Calculation of DPA in the Reactor Internal Structural Materials of Nuclear Power Plant

International Nuclear Information System (INIS)

Kim, Yong Deong; Lee, Hwan Soo

2014-01-01

The embrittlement is mainly caused by atomic displacement damage due to irradiations with neutrons, especially fast neutrons. The integrity of the reactor internal structural materials has to be ensured over the reactor life time, threatened by the irradiation induced displacement damage. Accurate modeling and prediction of the displacement damage is a first step to evaluate the integrity of the reactor internal structural materials. Traditional approaches for analyzing the displacement damage of the materials have relied on tradition model, developed initially for simple metals, Kinchin and Pease (K-P), and the standard formulation of it by Norgett et al. , often referred to as the 'NRT' model. An alternative and complementary strategy for calculating the displacement damage is to use MCNP code. MCNP uses detailed physics and continuous-energy cross-section data in its simulations. In this paper, we have performed the evaluation of the displacement damage of the reactor internal structural materials in Kori NPP unit 1 using detailed Monte Carlo modeling and compared with predictions results of displacement damage using the classical NRT model. The evaluation of the displacement damage of the reactor internal structural materials in Kori NPP unit 1 using detailed Monte Carlo modeling has been performed. The maximum value of the DPA rate was occurred at the baffle side of the reactor internal where the node has the maximum neutron flux

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.)

The DARPA manufacturing initiative in high temperature superconductivity

International Nuclear Information System (INIS)

Adams, K.R.

1989-01-01

The Defense Advanced Research Projects Agency (DARPA) has a very aggressive Technology Base program in high temperature superconductivity. This program is expected to provide the basis for a specialized set of military products - passive microwave and millimeter wave devices - within the next three years. In order to get these high leverage products into military systems, a manufacturing base must be developed for HTSC components. A plan for DARPA in HTSC manufacturing is directly coupled with the ongoing DARPA materials and device oriented R and D program. In essence, this plan recommends a three phased effort: 1. Phase I (two years); Fund companies through R and D contracts for specialized HTSC components; prepare a detailed plan and develop an HTSC consortium. 2. Phase II (six years): Establish an HTSC Sematech initiative for electronic applications, including active devices. 3. Phase III (optional): Continue the HTSC Sematech with emphasis on high power applications

Heat-resistant materials 2. Conference proceedings of the 2. international conference on heat-resistant materials

International Nuclear Information System (INIS)

Natesan, K.; Ganesan, P.; Lai, G.Y.

1995-01-01

The Second International Conference on Heat-Resistant Materials was held in Gatlinburg, Tennessee, September 11--14, 1995 and focused on materials performance in cross-cutting technologies where heat resistant materials play a large and sometimes life-and performance-limiting roles in process schemes. The scope of materials for heat-resistant applications included structural iron- and nickel-base alloys, intermetallics, and ceramics. The conference focused on materials development, performance of materials in simulated laboratory and actual service environments on mechanical and structural integrity of components, and state-of-the-art techniques for processing and evaluating materials performance. The three keynote talks described the history of heat-resistant materials, relationship between microstructure and mechanical behavior, and applications of these materials in process schemes. The technical sessions included alloy metallurgy and properties, environmental effects and properties, deformation behavior and properties, relation between corrosion and mechanical properties, coatings, intermetallics, ceramics, and materials for waste incineration. Seventy one papers have been processed separately for inclusion on the data base

Characterization of Decommissioned PWR Vessel Internals Materials Samples: Material Certification, Fluence, and Temperature (Nonproprietary Version)

International Nuclear Information System (INIS)

Krug, M.; Shogan, R.; Fero, A.; Snyder, M.

2004-01-01

Pressurized water reactor (PWR) cores, operate under extreme environmental conditions due to coolant chemistry, operating temperature, and neutron exposure. Extending the life of PWRs require detailed knowledge of the changes in mechanical and corrosion properties of the structural austenitic stainless steel components adjacent to the fuel. This report contains basic material characterization information of the as-installed samples of reactor internals material which were harvested from a decommissioned PWR

An international interdisciplinary graduate school in laser and material science

Science.gov (United States)

Fargin, Evelyne; Sarger, Laurent; Kaluza, Malte; Nolte, Stefan; Richardson, Martin; Richardson, Kathleen

2009-06-01

The main objective is to establish the first transatlantic Graduate School, proposing a truly international education, training and research platform in the field of Photonics and Material sciences. The wide scope of Photonics encompasses many application fields that will be mostly covered by various curricula involving Laser Optics and Material Sciences and Interactions. This cooperation will build a very efficient scientific international community able to address the 21 century challenges in Photonics and applications. Indeed, the highest level of education, namely Master and PhD , will address the so called "Skill shortage" that impact on our economy. The truly interdisciplinary theme of this graduate school is also a guarantee for the insertion of the graduate into the workforce.

International Nuclear Safety Center database on thermophysical properties of reactor materials

International Nuclear Information System (INIS)

Fink, J.K.; Sofu, T.; Ley, H.

1997-01-01

The International Nuclear Safety Center (INSC) database has been established at Argonne National Laboratory to provide easily accessible data and information necessary to perform nuclear safety analyses and to promote international collaboration through the exchange of nuclear safety information. The INSC database, located on the World Wide Web at http://www.insc.anl.gov, contains critically assessed recommendations for reactor material properties for normal operating conditions, transients, and severe accidents. The initial focus of the database is on thermodynamic and transport properties of materials for water reactors. Materials that are being included in the database are fuel, absorbers, cladding, structural materials, coolant, and liquid mixtures of combinations of UO 2 , ZrO 2 , Zr, stainless steel, absorber materials, and concrete. For each property, the database includes: (1) a summary of recommended equations with uncertainties; (2) a detailed data assessment giving the basis for the recommendations, comparisons with experimental data and previous recommendations, and uncertainties; (3) graphs showing recommendations, uncertainties, and comparisons with data and other equations; and (4) property values tabulated as a function of temperature

Materials management in an internationally safeguarded fuels reprocessing plant

International Nuclear Information System (INIS)

Hakkila, E.A.; Cobb, D.D.; Dayem, H.A.; Dietz, R.J.; Kern, E.A.; Markin, J.T.; Shipley, J.P.; Barnes, J.W.; Scheinman, L.

1980-04-01

The first volume of this report summarizes the results and conclusions for this study of conventional and advanced nuclear materials accounting systems applicable for both large (1500 MTHM/y) and small (210 MTHM/y) spent-fuel reprocessing facilities subject to international verification

IFMIF - International Fusion Materials Irradiation Facility Conceptual Design Activity/Interim Report

International Nuclear Information System (INIS)

Rennich, M.J.

1995-12-01

Environmental acceptability, safety, and economic viability win ultimately be the keys to the widespread introduction of fusion power. This will entail the development of radiation- resistant and low- activation materials. These low-activation materials must also survive exposure to damage from neutrons having an energy spectrum peaked near 14 MeV with annual radiation doses in the range of 20 displacements per atom (dpa). Testing of candidate materials, therefore, requires a high-flux source of high energy neutrons. The problem is that there is currently no high-flux source of neutrons in the energy range above a few MeV. The goal, is therefore, to provide an irradiation facility for use by fusion material scientists in the search for low-activation and damage-resistant materials. An accellerator-based neutron source has been established through a number of international studies and workshops' as an essential step for materials development and testing. The mission of the International Fusion Materials Irradiation Facility (IFMIF) is to provide an accelerator-based, deuterium-lithium (D-Li) neutron source to produce high energy neutrons at sufficient intensity and irradiation volume to test samples of candidate materials up to about a full lifetime of anticipated use in fusion energy reactors. would also provide calibration and validation of data from fission reactor and other accelerator-based irradiation tests. It would generate material- specific activation and radiological properties data, and support the analysis of materials for use in safety, maintenance, recycling, decommissioning, and waste disposal systems

PREFACE: 3rd International Symposium on Functional Materials 2009 (ISFM 2009) 3rd International Symposium on Functional Materials 2009 (ISFM 2009)

Science.gov (United States)

Kiwon, Kim; Li, Lu; Taehyun, Nam; Jouhyeon, Ahn

2010-05-01

The 3rd International Symposium on Functional Materials 2009 (ISFM 2009) and its preconference, Advances in Functional Materials 2009 (AFM 2009), were successfully held in the Republic of Korea from 15-18 June 2009 and in the People's Republic of China from 8-12 June 2009, respectively. The two conferences attracted over 300 oral and poster presentations from over 12 countries including Australia, Canada, China, Germany, Japan, India, Israel, Korea, The Netherlands, Thailand, the UK and the USA. In the two conferences, eight keynote lectures were delivered by S Miyazaki, S A Akbar, D J Singh, C Suryanarayana, M~Greenblatt, H Zhang, T Sato and J Ding. This topical issue of Physica Scripta contains papers presented at the ISFM 2009 and AFM 2009. Keyan Li from Dalian University, People's Republic of China, presents some empirical formulae to estimate the elastic moduli of rocksalt-, zincblende- and chalcopyrite-structured crystals, on the basis of electronegativities of bonded atoms in the crystallographic frame. Min-Jung Kim from Hanyang University, Korea, reports on the preparation and characterization of carboxyl functionalization of magnetite nanoparticles for oligonucleotide immobilization. F Yan from the National University of Singapore studies the fabrication of Bi(Fe0.5Sc0.5)O3-PbTiO3 (BSF-PT) thin films by pulsed laser deposition, and the enhanced magnetic moment with respect to BiFeO3-PbTiO3. Dong-Gil Lee from Pusan National University, Korea, reports on the sterilization of enteropathogenic Escherichia coli using nanofiber TiO2 films prepared by the electrostatic spray method. Sang-Eun Park from the Korea Institute of Science and Technology reports on the study of encapsulated Fe3O4 nanoparticles with a silica thin layer with a reversible capacity of about 363 mAhg-1. Other researchers report on many other exiting achievements in the fields of ferromagnetic materials, magneto-optical materials, thermoelectric materials, shape memory materials, fuel-cell and

International safeguards: Accounting for nuclear materials

Energy Technology Data Exchange (ETDEWEB)

Fishbone, L.G.

1988-09-28

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

International safeguards without material balance areas

International Nuclear Information System (INIS)

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

1992-01-01

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

International safeguards: Accounting for nuclear materials

International Nuclear Information System (INIS)

Fishbone, L.G.

1988-01-01

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

PRODUCING NEW SALES MATERIAL FOR INTERNATIONAL SALES OF HOLIDAY CLUB KATINKULTA

OpenAIRE

Sipilä, Marjo

2011-01-01

The aim of this action based thesis was to create new sales material in English for international sales of Holiday Club Katinkulta. The material concentrates on the services offered in the spa hotel side. The spa hotel was sold to its former owner Holiday Club Resorts ltd during the thesis writing process and all sales material required updating after the ownership change. The new sales material is produced for the aid of daily sales work of sales representatives in the field of internati...

Utilization of Additive Manufacturing in Evaluating the Performance of Internally Defected Materials

Science.gov (United States)

Mourad, A.-H. I.; Ghazal, A. M.; Syam, M. M.; Qadi, O. D. Al; Jassmi, H. Al

2018-05-01

The elimination of internal defects in a material present in the raw material or generated during the manufacturing or service is difficult. The inclusions of the defects have an adverse effect on the load bearing capacity. The presence of the cracks subjected to a specific orientation in materials or machinery can cause devastating unexpected failure during operation. Analysis of the failure in the components with cracks is more confined to analytical and numerical evaluation. The experimental evaluation has been tedious due to the complexity of replicating the actual defected component. The potential of additive manufacturing in developing user-defined components with cracks for the experimental evaluation is explored in this research. The present research investigated the effect of the internal elliptical cracks aligned at different orientations on the mechanical performance of polylactic acid (Green filament). The Fusion Deposition Method was utilized for the development of the standard tensile specimens with internal elliptical crack oriented at 0°, 45° and 90° using UltiMaker 2. The results proved that there is a considerable reduction in the load bearing capacity due to the presence of the cracks. The maximum load bearing capacity decreased by 15.01% for the specimen with crack inclined at 0° to the lateral axis compared to crack- free specimen. The nature of the fracture and the stress-strain graph evidently showcase the brittle nature of the material. The SEM image of the fractured region proved the phenomenal characteristics such as strong adhesion between the layers and the proper material flow. In the light of the results of this work, it can be concluded that the 3-D printing methodology is effective for evaluating the mechanical performance of the internally defected material.

International Conference on Recent Trends in Materials and Devices

CERN Document Server

Rattan, Sunita; Verma, Abhishek

2017-01-01

This book presents the proceedings of the International Conference on Recent Trends in Materials and Devices, which was conceived as a major contribution to large-scale efforts to foster Indian research and development in the field in close collaboration with the community of non-resident Indian researchers from all over the world. The research articles collected in this volume - selected from among the submissions for their intrinsic quality and originality, as well as for their potential value for further collaborations - document and report on a wide range of recent and significant results for various applications and scientific developments in the areas of Materials and Devices. The technical sessions covered include photovoltaics and energy storage, semiconductor materials and devices, sensors, smart and polymeric materials, optoelectronics, nanotechnology and nanomaterials, MEMS and NEMS, as well as emerging technologies.

International Congress on Energy Efficiency and Energy Related Materials

CERN Document Server

Bahsi, Zehra; Ozer, Mehmet; ENEFM2013

2014-01-01

The International Congress on Energy Efficiency and Energy Related Materials (ENEFM2013) was held on 9-12 October, 2013. This three-day congress focused on the latest developments of sustainable energy technologies, materials for sustainable energy applications and environmental & economic perspectives of energy. These proceedings include 63 peer reviewed technical papers, submitted from leading academic and research institutions from over 23 countries, representing some of the most cutting edge research available. The papers included were presented at the congress in the following sessions: General Issues Wind Energy Solar Energy Nuclear Energy Biofuels and Bioenergy Energy Storage Energy Conservation and Efficiency Energy in Buildings   Economical and Environmental Issues Environment Energy Requirements Economic Development   Materials for Sustainable Energy Hydrogen Production and Storage Photovoltaic Cells Thermionic Converters Batteries and Superconductors Phase Change Materials Fuel Cells Supercon...

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

International Nuclear Information System (INIS)

Larrimore, J.A.

1995-01-01

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

Benchmark studies of the effectiveness of structural and internal materials as radiation shielding for the international space station

Science.gov (United States)

Miller, J.; Zeitlin, C.; Cucinotta, F. A.; Heilbronn, L.; Stephens, D.; Wilson, J. W.

2003-01-01

Accelerator-based measurements and model calculations have been used to study the heavy-ion radiation transport properties of materials in use on the International Space Station (ISS). Samples of the ISS aluminum outer hull were augmented with various configurations of internal wall material and polyethylene. The materials were bombarded with high-energy iron ions characteristic of a significant part of the galactic cosmic-ray (GCR) heavy-ion spectrum. Transmitted primary ions and charged fragments produced in nuclear collisions in the materials were measured near the beam axis, and a model was used to extrapolate from the data to lower beam energies and to a lighter ion. For the materials and ions studied, at incident particle energies from 1037 MeV/nucleon down to at least 600 MeV/nucleon, nuclear fragmentation reduces the average dose and dose equivalent per incident ion. At energies below 400 MeV/nucleon, the calculation predicts that as material is added, increased ionization energy loss produces increases in some dosimetric quantities. These limited results suggest that the addition of modest amounts of polyethylene or similar material to the interior of the ISS will reduce the dose to ISS crews from space radiation; however, the radiation transport properties of ISS materials should be evaluated with a realistic space radiation field. Copyright 2003 by Radiation Research Society.

The problem of material accountancy. Difference between the international material accountancy and the Japanese material accountancy

International Nuclear Information System (INIS)

Ikawa, Koji

2001-01-01

It has been 30 years since the development of SSAC (State's system of Accounting for and Control of nuclear material) of Japan began. Moreover, 24 years have been passed after SSAC was employed. The maintenance on the law for carrying out SSAC in the meantime also progressed, and the system of SSAC has also been established favorably. However, new correspondence was internationally called for about the safeguards for reprocessing facilities or uranium enrichment facilities, and innovative safeguards concepts like NRTA or LFUA were developed. The LASCAR (Large Scale Reprocessing Plant Safeguards) forum was held on the safeguards for a large scale reprocessing facility, and international agreement on the safeguards was progressed. When we look back upon the history of such safeguards development in recent years, most people can see little problem on the contents of the national safeguards system itself. As the history shows, however, the passive approach has been taken in developing the Japanese safeguards system. We have always tried to seek a solution on the basis 'What is the minimum requirement in order to receive international safeguards.' Now, the nuclear fuel cycle of Japan has reached the maximum scale in the world. To Japan which promotes commercial use of plutonium, the world community is supervising this severely. Under such a situation it is no doubt that passive safeguards correspondence can no longer be allowed. The author thinks that it is coming when the old nuclear management system completed based on a passive attitude should be improved. What should an active nuclear material management system be? In this presentation, the author wishes to explore the clue to it. (author)

International Law and the Society of Nations: An Introduction to Public International Law in the 1990s. Cases and Materials.

Science.gov (United States)

King, Jason Scott, Ed.; Scurti, Jason, Ed.; And Others

This casebook on international law was developed by high school students around the globe and emphasizes the important role that students can play in furthering international law education. The text provides teachers and students with a summary review of 25 major cases heard by the International Court of Justice, along with additional materials.…

Computer system for International Reactor Pressure Vessel Materials Database support

International Nuclear Information System (INIS)

Arutyunjan, R.; Kabalevsky, S.; Kiselev, V.; Serov, A.

1997-01-01

This report presents description of the computer tools for support of International Reactor Pressure Vessel Materials Database developed at IAEA. Work was focused on raw, qualified, processed materials data, search, retrieval, analysis, presentation and export possibilities of data. Developed software has the following main functions: provides software tools for querying and search of any type of data in the database; provides the capability to update the existing information in the database; provides the capability to present and print selected data; provides the possibility of export on yearly basis the run-time IRPVMDB with raw, qualified and processed materials data to Database members; provides the capability to export any selected sets of raw, qualified, processed materials data

International Conference on Recent Trends in Materials Science and Applications

CERN Document Server

2017-01-01

This book gathers the proceedings of the plenary sessions, invited lectures, and papers presented at the International Conference on Recent Trends in Materials Science and Applications (ICRTMSA-2016). It also features revealing presentations on various aspects of Materials Science, such as nanomaterials, photonic crystal fibers, quantum dots, thin film techniques, crystal growth, spectroscopic procedures, fabrication and characterisation of new materials / compounds with enhanced features, and potential applications in nonlinear optical and electro-optic devices, solar cell device, chemical sensing, biomedical imaging, diagnosis and treatment of cancer, energy storage device etc. This book will be of great interest to beginning and seasoned researchers alike.

Preface: 10th International Symposium on Knappable Materials

Directory of Open Access Journals (Sweden)

Xavier Mangado Llach

2016-03-01

Full Text Available The University of Barcelona hosted from 7 to 11 September 2015, the International Symposium on Knappable Materials at the Building of the Faculty of Geography and History in the Raval campus in the city centre. The pleasant atmosphere of research and exchange of knowledge and experience was due in large part to the hard work and outstanding management and organizational skills of the institutions and individuals involved.

Study on CPPNM Interpretation of the Physical Protection Regulatory Aspects for International Transport of Nuclear Material

Energy Technology Data Exchange (ETDEWEB)

Kim, Woo-jin; Yang, Seong-hyo; Hyung, Sang-chul [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

2015-05-15

Nuclear energy has been regulated by various international agreements or treaties due to the potential dangers. In case of export or import of nuclear material, it is important to comply with international norms and domestic laws related to nonproliferation and physical protection of nuclear material. Because, if non-compliant, it can be taken nuclear sanctions from the international community, and thus the domestic nuclear activities can be under a negative impact. Recently, international interests in nuclear security have been increased, it has become very sensitive to whether or not to join, and to comply with international treaties during international transportation of nuclear materials. Currently it is not discussed yet how to present and interpret the relevant provisions in CPPNM. However, it is necessary to prepare for the dispute among the parties that we don't know when it happens.

International Workshop on Best Practices in Material Hold-Up Monitoring

International Nuclear Information System (INIS)

Pickett, Chris A; Coates, Cameron W.

2008-01-01

In the fall of 2006, the Oak Ridge National Laboratory (ORNL) hosted an INMM-sponsored International Workshop on Best Practices in Material Hold-Up Monitoring. This workshop represented the first time in over 20 years that the international community had gathered to discuss pertinent hold-up topics and needs. More than one hundred people attended the workshop. Their expertise in the field ranged from novice to expert, and they shared their experiences and expertise throughout the week of the workshop. Presenters discussed techniques that have been used worldwide to detect and characterize nuclear materials held up in processes and equipment and the policies used to report quantities detected. The primary goal of the workshop was to compile information on the best practices and lessons learned and to make this information available for sharing throughout the international community. This paper discusses the information that was produced from four separate working groups (each composed of workshop attendees). Each group was tasked to determine what it felt to be the best practices in the field today and what issues needed to be addressed to move the field forward in the 21st century

10th International School of Materials Science and Technology : Intercalation in Layered Materials "Ettore Majorana"

CERN Document Server

1986-01-01

This volume is prepared from lecture notes for the course "Intercalation in Layered Materials" which was held at the Ettore Majorana Centre for Scientific Culture at Erice, Sicily in July, 1986, as part of the International School of Materials Science and Tech­ nology. The course itself consisted of formal tutorial lectures, workshops, and informal discussions. Lecture notes were prepared for the formal lectures, and short summaries of many of the workshop presentations were prepared. This volume is based on these lecture notes and research summaries. The material is addressed to advanced graduate students and postdoctoral researchers and assumes a background in basic solid state physics. The goals of this volume on Intercalation in Layered Materials include an introduc­ tion to the field for potential new participants, an in-depth and broad exposure for stu­ dents and young investigators already working in the field, a basis for cross-fertilization between workers on various layered host materials...

Mechanical properties and internal fit of 4 CAD-CAM block materials.

Science.gov (United States)

Goujat, Alexis; Abouelleil, Hazem; Colon, Pierre; Jeannin, Christophe; Pradelle, Nelly; Seux, Dominique; Grosgogeat, Brigitte

2018-03-01

Recent polymer-based computer-assisted design and computer-assisted manufacturing (CAD-CAM) materials have been commercialized for inlay restorations, a polymer-infiltrated ceramic-network (PICN) and composite resin nanoceramics. Little independent evidence regarding their mechanical properties exists. Internal adaptation is an important factor for the clinical success and longevity of a restoration, and data concerning this parameter for inlays made with these blocks are scarce. The purpose of this in vitro study was to evaluate and compare the mechanical properties (flexural strength, flexural modulus, Vickers hardness, fracture toughness) and the internal adaptation of these recent polymer-based blocks with a lithium disilicate glass-ceramic block. The materials tested in this study were a PICN material (Vita Enamic), 2 composite resin nanoceramics (Lava Ultimate; 3M ESPE and Cerasmart; GCDental Products), and a lithium disilicate glass-ceramic (IPS e.max CAD). Mechanical properties were evaluated according to ISO norm DIS 6872:2013. Bar-shaped specimens (18×3×3 mm) were prepared and submitted to a 3-point bend test using a universal testing machine at a cross-head speed of 0.5 mm/min. In addition, identical cavities were prepared in 60 human mandibular extracted molars (n=15) and optically scanned to receive mesioocclusodistal inlays milled with the 4 materials tested in a CEREC Inlab milling machine. The replica technique and a stereomicroscope (×20) were used to measure the internal fit of the inlays at 9 preselected locations. All data were statistically analyzed using 1-way ANOVA and the post hoc Tukey multiple comparison or Games-Howell test (α=.05). The mean flexural strength of the tested blocks ranged from 148.7 ±9.5 MPa (Vita Enamic) to 216.5 ±28.3 MPa (Cerasmart). The mean flexural modulus ranged from 23.3 ±6.4 GPa (Vita Enamic) to 52.8 ±10.5 GPa (IPS e.max CAD). The mean Vickers hardness ranged from 0.66 ±0.02 GPa (Cerasmart) to 5.98 ±0

Development of nuclear materials accounting for international safeguards

International Nuclear Information System (INIS)

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

1991-01-01

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

Theorising international monetary relations: three questions about the significance of materiality

Directory of Open Access Journals (Sweden)

Anna Leander

2015-12-01

Full Text Available Abstract This article engages a conversation with Benjamin Cohen by raising three questions about the significance of materiality. The paper's questions focus on how materiality can be included in theorizations so that its political import is not defined away from the outset. The article does this focussing on Cohen's treatment of electronic money and its significance for the Politics of International Monetary Relations. The first question posed is about ontology, the second about agency and the third about the scope of politics. The three questions are raised as a conversation in which arguments and counterarguments are advanced. The questions are therefore posed with Cohen's contributions to theorizing the political significance of materiality as their point of departure. They are formulated as a consequence of bringing these contributions in relation to insights from the Social Studies of Finance. From this perspective it would seem that a more far reaching engagement with materiality (in terms of ontology, agency and epistemology is necessary to capture its political significance for international monetary politics and currency hierarchies. The article does not conclude in conventional fashion but purposefully strives to leave these questions open for discussion.

Neutronics analysis of International Fusion Material Irradiation Facility (IFMIF). Japanese contributions

International Nuclear Information System (INIS)

Oyama, Yukio; Noda, Kenji; Kosako, Kazuaki.

1997-10-01

In fusion reactor development for demonstration reactor, i.e., DEMO, materials tolerable for D-T neutron irradiation are absolutely required for both mechanical and safety point of views. For this requirement, several kinds of low activation materials were proposed. However, experimental data by actual D-T fusion neutron irradiation have not existed so far because of lack of fusion neutron irradiation facility, except fundamental radiation damage studies at very low neutron fluence. Therefore such a facility has been strongly requested. According to agreement of need for such a facility among the international parties, a conceptual design activity (CDA) of International Fusion Material Irradiation Facility (IFMIF) has been carried out under the frame work of the IEA-Implementing Agreement. In the activity, a neutronics analysis on irradiation field optimization in the IFMIF test cell was performed in three parties, Japan, US and EU. As the Japanese contribution, the present paper describes a neutron source term as well as incident deuteron beam angle optimization of two beam geometry, beam shape (foot print) optimization, and dpa, gas production and heating estimation inside various material loading Module, including a sensitivity analysis of source term uncertainty to the estimated irradiation parameters. (author)

International workshop on advanced materials for high precision detectors. Proceedings

International Nuclear Information System (INIS)

Nicquevert, B.; Hauviller, C.

1994-01-01

These proceedings gather together the contributions to the Workshop on Advanced Materials for High Precision Detectors, which was held from 28-30 September 1994 in Archamps, Haute-Savoie, France. This meeting brought together international experts (researchers, physicists and engineers) in the field of advanced materials and their use in high energy physics detectors or spacecraft applications. Its purpose was to discuss the status of the different materials currently in use in the structures of detectors and spacecraft, together with their actual performances, technological implications and future prospects. Environmental effects, such as those of moisture and radiation, were discussed, as were design and manufacturing technologies. Some case studies were presented. (orig.)

Contributions to the sixth international conference on fusion reactor materials

Energy Technology Data Exchange (ETDEWEB)

NONE

1993-11-15

The ICFRM series has documented progress in the field of fusion reactor materials since the first conference held in Tokyo in 1984. The conference series has continually increased its coverage to the point where it now includes the comprehensive range of materials science and technology areas that enable systems designers to meet the needs of current experiments and to present innovative solutions for future energy systems. This publication contains five contributions to the sixth international conference which have each been indexed separately.

2nd International Conference on Rheology and Modeling of Materials (IC-RMM2)

International Nuclear Information System (INIS)

2017-01-01

Understanding the rheological properties of materials and their rheological behaviors during their manufacturing processes and in their applications in many cases can help to increase the efficiency and competitiveness not only of the finished goods and products but the organizations and societies also. The more scientific supported and prepared organizations develop more competitive products with better thermal, mechanical, physical, chemical and biological properties and the leading companies apply more competitive equipment and technology processes. The aims of the 2 nd International Conference on Rheology and Modeling of Materials (ic-rmm2) and the parallel organized symposiums of the 1 st International Symposium on Powder Injection Molding (is-pim1) and the 1 st International Symposium on Rheology and Fracture of Solids (is-rfs1) are the followings: Promote new methods and results of scientific research in the fields of modeling and measurements of rheological properties and behavior of materials under processing and applications; Change information between the theoretical and applied sciences as well as technical and technological implantations. Promote the communication and collaboration between the scientists, researchers and engineers of different disciplines, different nations, countries and continents. The international conference ic-rmm2 and symposiums of is-pim1 and is-rfs1 provide a platform among the leading international scientists, researchers, PhD students and engineers for discussing recent achievements in measurement, modeling and application of rheology in materials technology and materials science of liquids, melts, solids, crystals and amorphous structures. Among thr major fields of interest are the influence of materials structures, mechanical stresses, temperatures, deformation speeds and shear rates on rheological and physical properties, phase transformation of foams, foods, polymers, plastics and other competitive materials like ceramics

2nd International Conference on Rheology and Modeling of Materials (IC-RMM2)

Science.gov (United States)

2017-01-01

Understanding the rheological properties of materials and their rheological behaviors during their manufacturing processes and in their applications in many cases can help to increase the efficiency and competitiveness not only of the finished goods and products but the organizations and societies also. The more scientific supported and prepared organizations develop more competitive products with better thermal, mechanical, physical, chemical and biological properties and the leading companies apply more competitive equipment and technology processes. The aims of the 2nd International Conference on Rheology and Modeling of Materials (ic-rmm2) and the parallel organized symposiums of the 1st International Symposium on Powder Injection Molding (is-pim1) and the 1st International Symposium on Rheology and Fracture of Solids (is-rfs1) are the followings: Promote new methods and results of scientific research in the fields of modeling and measurements of rheological properties and behavior of materials under processing and applications; Change information between the theoretical and applied sciences as well as technical and technological implantations. Promote the communication and collaboration between the scientists, researchers and engineers of different disciplines, different nations, countries and continents. The international conference ic-rmm2 and symposiums of is-pim1 and is-rfs1 provide a platform among the leading international scientists, researchers, PhD students and engineers for discussing recent achievements in measurement, modeling and application of rheology in materials technology and materials science of liquids, melts, solids, crystals and amorphous structures. Among thr major fields of interest are the influence of materials structures, mechanical stresses, temperatures, deformation speeds and shear rates on rheological and physical properties, phase transformation of foams, foods, polymers, plastics and other competitive materials like ceramics

Safety of radiation sources and security of radioactive materials. Proceedings of an international conference

International Nuclear Information System (INIS)

1999-01-01

This International Conference, hosted by the Government of France and co-sponsored by the European Commission, the International Criminal Police Organization (Interpol) and the World Customs Organization (WCO), was the first one devoted to the safety of radiation sources and the security of radioactive materials and - for the first time - brought together radiation safety experts, regulators, and customs and police officers, who need to closely co-operate for solving the problem of illicit trafficking. The technical sessions reviewed the state of the art of twelve major topics, divided into two groups: the safety of radiation sources and the security of radioactive materials. The safety part comprised regulatory control, safety assessment techniques, engineering and managerial measures, lessons from experience, international cooperation through reporting systems and databases, verification of safety through inspection and the use of performance indicators for a regulatory programme. The security part comprised measures to prevent breaches in the security of radioactive materials, detection and identification techniques for illicit trafficking, response to detected cases and seized radioactive materials, strengthening awareness, training and exchange of information. The Conference was a success in fostering information exchange through the reviews of the state of the art and the frank and open discussions. It raised awareness of the need for Member States to ensure effective systems of control and for preventing, detecting and responding to illicit trafficking in radioactive materials. The Conference finished by recommending investigating whether international undertakings concerned with an effective operation of national systems for ensuring the safety of radiation sources and security of radioactive materials

International cooperation in combating illicit trafficking of nuclear materials by technical means

International Nuclear Information System (INIS)

Herbillon, J; Koch, L; Mason, G; Niemeyer, S; Nikiforov, N

1999-01-01

A consensus has been emerging during the past several years that illicit trafficking of nuclear materials is a problem that needs a more focused international response. One possible component of a program to combat illicit trafficking is nuclear forensics whereby intercepted nuclear materials are analyzed to provide clues for answering attribution questions. In this report we focus on international cooperation that is specifically addressing the development of nuclear forensics. First we will describe the role of the Nuclear Smuggling International Technical Working Group (ITWG) in developing nuclear forensics, and then we will present some specific examples of cooperative work by the Institute for Transuranium Elements of the European Commission with various European states. Recognizing the potential importance of a nuclear forensics capability, the P-8 countries in 1995 encouraged technical experts to evaluate the role of nuclear forensics in combating nuclear smuggling and possibly developing mechanisms for international cooperation. As a result, an International Conference on Nuclear Smuggling Forensic Analysis was held in November, 1995, at Lawrence Livermore National Laboratory to investigate technical cooperation on nuclear forensics. The International Conference provided a unique mix of scientists, law enforcement, and intelligence experts from 14 countries and organizations. All participants were invited to make presentations, and the format of the Conference was designed to encourage open discussion and broad participation

Modeling Electrostatic Fields Generated by Internal Charging of Materials in Space Radiation Environments

Science.gov (United States)

Minow, Joseph I.

2011-01-01

Internal charging is a risk to spacecraft in energetic electron environments. DICTAT, NU MIT computational codes are the most widely used engineering tools for evaluating internal charging of insulator materials exposed to these environments. Engineering tools are designed for rapid evaluation of ESD threats, but there is a need for more physics based models for investigating the science of materials interactions with energetic electron environments. Current tools are limited by the physics included in the models and ease of user implementation .... additional development work is needed to improve models.

The recent international situation on the transport of radioactive material and IAEA 2003 transport conference

International Nuclear Information System (INIS)

Tani, Hiroshi

2003-01-01

Since the creation of the United Nations, the international community initiated efforts to harmonize international practices for the safe transport of hazardous goods, including radioactive material. And, IAEA is playing a key role in fostering the establishment of transport regulations on radioactive material. This current worldwide system of regulatory control has achieved an excellent safety record. However, some concerns still remain regarding the transport of radioactive material, as the discussion of this topic at IAEA General Conferences in the last few years. IAEA Transport conference planed as a forum in which to better understand these concerns, and to answer relevant underlying questions. At the same time, outside these technical areas, discussions also covered related issues such as liability resulting from an accident during the transport and communication between concerned governments, and between these governments and the public at large. The International Conference on the Safety of Transport of Radioactive Material took place in Vienna, Austria, from 7 to 11 July 2003. There were 534 nominated participants from 82 States, 9 intergovernmental organizations (IGOs), and 5 non-governmental organizations (NGOs), and there were 132 contributed and invited papers. By this report, I report the recent international situation on the transport of radioactive material and result of the IAEA 2003 Transport Conference. (author)

Development of international standards for instrumentation used for detection of illicit trafficking of radioactive material

International Nuclear Information System (INIS)

Voytchev, M.; Chiaro, P.; Radev, R.

2006-01-01

Subcommittee 45 B 'Radiation Protection Instrumentation' of the International Electrotechnical Commission (I.E.C.) is charged with the development of international standards for instrumentation used for monitoring of illicit trafficking of radioactive material through international boarders and territories, as well as inside countries. Currently three I.E.C. standards are in advanced stages of development. They are expected to be approved and published in 2006-2007. The international participation and the main characteristics of the following three standards are discussed and presented: I.E.C. 62327 'Hand-held Instruments for the Detection and Identification of Radionuclides and Additionally for the Indication of Ambient Dose Equivalent Rate from Photon Radiation', I.E.C. 62401 'Alarming Personal Radiation Devices for Detection of Illicit Trafficking of Radioactive Material' and I.E.C. 62244 'Installed Radiation Monitors for the Detection of Radioactive and Special Nuclear Materials at National Borders'

The nuclear materials control and accountability internal audit program at the Oak Ridge Y-12 plant

International Nuclear Information System (INIS)

Lewis, T.J.

1987-01-01

The internal audit program of the Nuclear Material Control and Accountability (NMCandA) Department at the Oak Ridge Y-12 Plant, through inventory-verification audits, inventory-observation audits, procedures audits, and records audits, evaluates the adequacy of material accounting and control systems and procedures throughout the Plant; appraises and verifies the accuracy and reliability of accountability records and reports; assures the consistent application of generally accepted accounting principles in accounting for nuclear materials; and assures compliance with the Department of Energy (DOE) and NMCandA procedures and requirements. The internal audit program has significantly strengthened the control and accountability of nuclear materials through improving the system of internal control over nuclear materials, increasing the awareness of materials control and accountability concerns within the Plant's material balance areas (MBAs), strengthening the existence of audit trails within the overall accounting system for nuclear materials, improving the accuracy and timeliness of data submitted to the nuclear materials accountability system, auditing the NMCandA accounting system to ensure its accuracy and reliability, and ensuring that all components of that system (general ledgers, subsidiary ledgers, inventory listings, etc.) are in agreement among themselves

INFOMAT: The international materials assessment and application centre's internet gateway

Science.gov (United States)

Branquinho, Carmen Lucia; Colodete, Leandro Tavares

2004-08-01

INFOMAT is an electronic directory structured to facilitate the search and retrieval of materials science and technology information sources. Linked to the homepage of the International Materials Assessment and Application Centre, INFOMAT presents descriptions of 392 proprietary databases with links to their host systems as well as direct links to over 180 public domain databases and over 2,400 web sites. Among the web sites are associations/unions, governmental and non-governmental institutions, industries, library holdings, market statistics, news services, on-line publications, standardization and intellectual property organizations, and universities/research groups.

Propagation of internal stresses in composite materials during heating and cooling according to thermal cycles of welding

International Nuclear Information System (INIS)

Gukasyan, L.E.; Belov, V.V.

1977-01-01

Investigations of free thermal expansion of a composite material, of fibre and matrix during welding thermal cycle make it possible to estimate mean internal strain and stress in the composite components, as well as the residual internal stress and strain present in the composite material after manufacturing. The samples investigated consisted of nickel-chromium EhI445 alloy, reinforced by tungsten-rhenium alloy fibres. As the composite material was cooled and heated in course of welding, the stress and strain changed their sign twice, the first time upon heating, the second time upon cooling. After complete cooling of the composite material residual stresses in the fibre stay at the proportionality level, while those in the matrix are lower. Experimental evidence of internal stress and strain appearing in the composite material during heating are fairly consistent with calculations in the elastic region, if account is taken of the temperature of internal residual stress relaxation upon heating

Stockholm conference. Summary of the international conference on the security of material in Stockholm, Sweden

International Nuclear Information System (INIS)

Hoskins, Richard

2001-01-01

Preventing illicit uses of nuclear material and radioactive sources was a major international concern even before the spectre of nuclear terrorism was raised by terrorist attacks in September 2001. At an IAEA international conference in Stockholm, Sweden, convened in May 2001, international experts examined ways and means of strengthening systems for the protection of nuclear and radioactive material. The Conference - formally called 'Security of Material: Measures to Prevent, Intercept and Respond to Illicit Uses of Nuclear Material and Radioactive Sources' - was attended by more than 300 experts from around the world. It was organized by the IAEA in cooperation with the European Police Office (Europol), the International Criminal Police Organization - Interpol (ICPO-Interpol), and the World Customs Organization (WCO), and hosted by the Swedish Nuclear Power Inspectorate. In the Conference Summary Document, participants underscored the importance of establishing stronger systems for nuclear security, and they outlined a number of steps for the future in particular areas. Following are excerpts from the Document. More information on the Conference is accessible on the IAEA's WorldAtom Web site at http://www.iaea.org/ worldatom/Press/P r elease/2001/ prn0110.shtml

Development of international standards for instrumentation used for detection of illicit trafficking of radioactive material

Energy Technology Data Exchange (ETDEWEB)

Voytchev, M. [Institut de Radioprotection et de Surete Nucleaire (IRSN/DSU/SERAC/CTHIR), 91 - Gif sur Yvette (France); Chiaro, P. [Oak Ridge National Lab., TN (United States); Radev, R. [LLNL, Livermore, CA (United States)

2006-07-01

Subcommittee 45 B 'Radiation Protection Instrumentation' of the International Electrotechnical Commission (I.E.C.) is charged with the development of international standards for instrumentation used for monitoring of illicit trafficking of radioactive material through international boarders and territories, as well as inside countries. Currently three I.E.C. standards are in advanced stages of development. They are expected to be approved and published in 2006-2007. The international participation and the main characteristics of the following three standards are discussed and presented: I.E.C. 62327 'Hand-held Instruments for the Detection and Identification of Radionuclides and Additionally for the Indication of Ambient Dose Equivalent Rate from Photon Radiation', I.E.C. 62401 'Alarming Personal Radiation Devices for Detection of Illicit Trafficking of Radioactive Material' and I.E.C. 62244 'Installed Radiation Monitors for the Detection of Radioactive and Special Nuclear Materials at National Borders'.

An investigation of structural design methodology for HTGR reactor internals with ceramic materials (Contract research)

International Nuclear Information System (INIS)

Sumita, Junya; Shibata, Taiju; Nakagawa, Shigeaki; Iyoku, Tatsuo; Sawa, Kazuhiro

2008-03-01

To advance the performance and safety of HTGR, heat-resistant ceramic materials are expected to be used as reactor internals of HTGR. C/C composite and superplastic zirconia are the promising materials for this purpose. In order to use these new materials as reactor internals in HTGR, it is necessary to establish a structure design method to guarantee the structural integrity under environmental and load conditions. Therefore, C/C composite expected as reactor internals of VHTR is focused and an investigation on the structural design method applicable to the C/C composite and a basic applicability of the C/C composite to representative structures of HTGR were carried out in this report. As the results, it is found that the competing risk theory for the strength evaluation of the C/C composite is applicable to design method and C/C composite is expected to be used as reactor internals of HTGR. (author)

International Commission on Nuclear Non-Proliferation and Disarmament - A possible international regime to cover radiological materials

International Nuclear Information System (INIS)

Hautecouverture, Benjamin

2009-10-01

Even if a 'dirty bomb' has never been used to date, the perception of the existence of a threat is shared by many. Four main types of radiological and nuclear terrorist attacks can be outlined: - acquisition and use of a nuclear weapon, - attacks and acts of sabotage against a nuclear reactor or another nuclear facility, - acquisition of fissile material for the elaboration of an Improvised Nuclear Device, - terrorist use of radiological materials for the elaboration of a Radiological Dispersal Device (RDD). This paper seeks to evaluate the probability for a terrorist group to acquire and make use of radiological materials in the objective of detonating a RDD, and the current international framework put into place to address such a threat. Is an international regime to cover radiological materials already in place? How comprehensive / integrated is it? Does a new and/or separate system need to be set up? Before 9/11, two events in particular served to illustrate the threat of a radiological or nuclear terrorist attack: Moscow in 1996, Argun in 1998. Since the 9/11 attacks, a few other radiological events have occurred, which could suggest that the threat is becoming more pressing. It must be noted that the use of a dirty bomb by a terrorist group would most probably be aimed at the contamination of a given geographical area, rather than mass destruction and killing. Indeed, the lethal impact of such weapons remains limited. For this reason, dirty bombs are considered by analysts as weapons of mass disruption rather than weapons of mass destruction. Impacts would be more important in the psychological or economic realms: - targeting highly populated environments, such as cities, would most probably not result in a high death toll; - compared with impacts on health, psychological impacts of such an attack would be much more serious, both within and outside the targeted population; - economic damage is probably the greatest threat posed by such attacks, particularly

A proposal for an international tagging system for radioactive materials

International Nuclear Information System (INIS)

Bahran, M.

2001-01-01

Full text: In an earlier paper based on our experience with lost or abundant radiation sources, we have discussed the need of an international tagging system for radioactive materials for the purpose of insuring trackability, accountability and safety. In this paper we take our discussion further by presenting a proposal of establishing such an international tagging system for radioactive materials which we call ITS-RM. The elements of ITS-RM: IAEA is to be the international authority in charge of ITS-RM; Each 'significant' radiation source is to be labeled with a unique number at the point of production. This number is identified as ITS-RM number; The term 'significant' can be defined in light of current international standards; As each source is naturally possessed by some legal notion or international entity, each time this entity is changed (e.g. the source is sold, resold, transported, decommissioned etc.) the process of changing hand is registered at IAEA via the ITS-RM number; No source is to change hands without triggering ITS-RM; Even if a source finds its way to a waste facility it will remain tagged indefinitely. The requirement for ITS-RM: Legal requirement: this issue needs to be studied to find out weather anew international treaty needs to be established or ITS-RM can be applied under existing treaties; Organizational requirements: This can be easily done with the framework if IAEA and national counterparts; Consultation requirements: ITS-RM can only work if it is done through complete consultation and cooperation with manufactures. Old and current sources: An effort is to be made to survey and tag current sources; Priorities will be given as follows: first to new sources second to current sources the comes last old sources, particularly those in storage facilities; ITS-RM is not to compete with any existing safety system, national or internationally, to the contrary is to support safety. ITS-RM advantages are many but in particular we have

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)

PREFACE: 1st International Conference in Applied Physics and Materials Science

Science.gov (United States)

2015-06-01

We are delighted to come up with thirty two (32) contributed research papers in these proceedings, focusing on Materials Science and Applied Physics as an output of the 2013 International Conference in Applied Physics and Materials Science (ICAMS2013) held on October 22-24, 2013 at the Ateneo de Davao University, Davao City, Philippines. The conference was set to provide a high level of international forum and had brought together leading academic scientists, industry professionals, researchers and scholars from universities, industries and government agencies who have shared their experiences, research results and discussed the practical challenges encountered and the solutions adopted as well as the advances in the fields of Applied Physics and Materials Science. This conference has provided a wide opportunity to establish multidisciplinary collaborations with local and foreign experts. ICAMS2013, held concurrently with 15th Samahang Pisika ng Visayas at Mindanao (SPVM) National Physics Conference and 2013 International Meeting for Complex Systems, was organized by the Samahang Pisika ng Visayas at Mindanao (Physics Society of Visayas and Mindanao) based in MSU-Iligan Institute of Technology, Iligan City, Philippines. The international flavor of converging budding researchers and experts on Materials Science and Applied Physics was the first to be organized in the 19 years of SPVM operation in the Philippines. We highlighted ICAMS2013 gathering by the motivating presence of Dr. Stuart Parkin, a British Physicist, as one of our conference's plenary speakers. Equal measures of gratitude were also due to all other plenary speakers, Dr. Elizabeth Taylor of Institute of Physics (IOP) in London, Dr. Surya Raghu of Advanced Fluidics in Maryland, USA and Prof. Hitoshi Miyata of Niigata University, Japan, Prof. Djulia Onggo of Institut Teknologi Bandung, Indonesia, and Dr. Hironori Katagiri of Nagaoka National College of Technology, Japan. The warm hospitality of the host

PREFACE: 2nd International Meeting for Researchers in Materials and Plasma Technology

Science.gov (United States)

Niño, Ely Dannier V.

2013-11-01

These proceedings present the written contributions of the participants of the 2nd International Meeting for Researchers in Materials and Plasma Technology, 2nd IMRMPT, which was held from February 27 to March 2, 2013 at the Pontificia Bolivariana Bucaramanga-UPB and Santander and Industrial - UIS Universities, Bucaramanga, Colombia, organized by research groups from GINTEP-UPB, FITEK-UIS. The IMRMPT, was the second version of biennial meetings that began in 2011. The three-day scientific program of the 2nd IMRMPT consisted in 14 Magisterial Conferences, 42 Oral Presentations and 48 Poster Presentations, with the participation of undergraduate and graduate students, professors, researchers and entrepreneurs from Colombia, Russia, France, Venezuela, Brazil, Uruguay, Argentina, Peru, Mexico, United States, among others. Moreover, the objective of IMRMPT was to bring together national and international researchers in order to establish scientific cooperation in the field of materials science and plasma technology; introduce new techniques of surface treatment of materials to improve properties of metals in terms of the deterioration due to corrosion, hydrogen embrittlement, abrasion, hardness, among others; and establish cooperation agreements between universities and industry. The topics covered in the 2nd IMRMPT include New Materials, Surface Physics, Laser and Hybrid Processes, Characterization of Materials, Thin Films and Nanomaterials, Surface Hardening Processes, Wear and Corrosion / Oxidation, Modeling, Simulation and Diagnostics, Plasma Applications and Technologies, Biomedical Coatings and Surface Treatments, Non Destructive Evaluation and Online Process Control, Surface Modification (Ion Implantation, Ion Nitriding, PVD, CVD). The editors hope that those interested in the are of materials science and plasma technology, enjoy the reading that reflect a wide range of topics. It is a pleasure to thank the sponsors and all the participants and contributors for

International fusion materials irradiation facility and neutronic calculations for its test modules

International Nuclear Information System (INIS)

Sokcic-Kostic, M.

1997-01-01

The International Fusion Material Irradiation Facility (IFMIF) is a projected high intensity neutron source for material testing. Neutron transport calculations for the IFMIF project are performed for variety of here explained reasons. The results of MCNP neutronic calculations for IFMIF test modules with NaK and He cooled high flux test cells are presented in this paper. (author). 3 refs., 2 figs., 3 tabs

Proceedings of the international symposium on materials testing reactors

International Nuclear Information System (INIS)

Ishihara, Masahiro; Kawamura, Hiroshi

2009-01-01

This report is the Proceedings of the International Symposium on Materials Testing Reactors hosted by Japan Atomic Energy Agency (JAEA). The symposium was held on July 16 to 17, 2008, at the Oarai Research and Development Center of JAEA. This symposium was also held for the 40th anniversary ceremony of Japan Materials Testing Reactor (JMTR) from achieving its first criticality. The objective of the symposium is to exchange the information on current status, future plan and so on among each testing reactors for the purpose of mutual understanding. There were 138 participants from Argentina, Belgium, France, Indonesia, Kazakhstan, Korea, the Russian Federation, Sweden, the United State, Vietnam and Japan. The symposium was divided into four technical sessions and three topical sessions. Technical sessions addressed the general topics of 'status and future plan of materials testing reactors', 'material development for research and testing reactors', irradiation technology (including PIE technology)' and 'utilization with materials testing reactors', and 21 presentations were made. Also the topical sessions addressed 'establishment of strategic partnership', 'management on re-operation work at reactor trouble' and 'basic technology for neutron irradiation tests in MTRs', and panel discussion was made. The 21 of the presented papers are indexed individually. (J.P.N.)

Internal transfers of special nuclear material - March 1975

International Nuclear Information System (INIS)

Anon.

1976-01-01

Paragraph 70.51(e) of 10 CFR Part 70 requires, with certain exceptions stated in the rule, that each licensee authorized to possess more than one effective kilogram of special nuclear material (SNM) maintain certain procedures. These procedures are to include: (1) records of the quantities of SNM added to or removed from the process; (2) documentation of all transfers of SNM between material-balance areas to show the identity and quantity of SNM transferred; (3) requirements for authorized signatures on each document used to record the transfer of SNM between material-balance areas; and (4) means for control of and accounting for internal transfer documents. Paragraph 70.58(e) requires licensees to establish, maintain, and follow a system for measuring the SNM transferred between material-balance areas and item-control areas. Paragraph 70.58(f) requires that licensees have a program that evaluates and controls the quality of their measurement system. Additionally, all licensees authorized to possess SNM must comply with paragraph 70.51(b) of 10 CFR Part 70. That rule requires licensees to keep records showing, among other things, the inventory of all SNM in their possession and its location. This guide sets forth acceptable methods for controlling and documenting transfers of SNM within a plant site in order to meet the requirements listed above

Method of using sacrificial materials for fabricating internal cavities in laminated dielectric structures

Science.gov (United States)

Peterson, Kenneth A [Albuquerque, NM

2009-02-24

A method of using sacrificial materials for fabricating internal cavities and channels in laminated dielectric structures, which can be used as dielectric substrates and package mounts for microelectronic and microfluidic devices. A sacrificial mandrel is placed in-between two or more sheets of a deformable dielectric material (e.g., unfired LTCC glass/ceramic dielectric), wherein the sacrificial mandrel is not inserted into a cutout made in any of the sheets. The stack of sheets is laminated together, which deforms the sheet or sheets around the sacrificial mandrel. After lamination, the mandrel is removed, (e.g., during LTCC burnout), thereby creating a hollow internal cavity in the monolithic ceramic structure.

Proceedings of the 26th International Cryogenic Engineering Conference - International Cryogenic Material Conference 2016

Science.gov (United States)

Datta, T. S.; Sharma, R. G.; Kar, S.

2017-02-01

International Conference ICEC 26 - ICMC 2016 was organized at New Delhi, India during March 7-11, 2016. Previous conference ICEC25-ICMC 2014 was held at the University of Twente, The Netherlands in July 2014. Next Conference ICEC 27- ICMC 2018 will be held at Oxford, UK during September 3-7, 2018 1. Introduction This is a biennial international conference on cryogenic engineering and cryogenics materials organized by the International Cryogenic Engineering Committee and the International Cryogenic Material Committee. For some years, the host country has been alternating between Europe and Asia. The present conference was held at the Manekshaw Convention Centre, New Delhi, India during March 7-11, 2016 and hosted jointly by the Indian Cryogenics Council (ICC) and the Inter-University Accelerator Centre (IUAC), New Delhi. Put all together as many as 547 persons participated in the conference. Out of these 218 were foreign delegates coming from 25 countries and the rest from India. 2. Inaugural Session & Course Lectures The pre conference short course lectures on “Cryocoolers” and “Superconducting Materials for Power Applications” were organized on 7th March. Cryocooler course was given jointly by Dr. Chao Wang from M/s. Cryomech, USA and Prof. Milind Atrey from IIT Bombay, India. The Course on Superconducting Materials was given by Prof. Venkat Selvamanickam from the University of Houston, USA. The conference was inaugurated in the morning of March 8th in a typical Indian tradition and in the presence of the Chief Guest, Dr. R Chidambaram (Principle Scientific Adviser to Govt. of India), Guest of Honour, Prof. H Devaraj (Vice Chairman University Grant Commission), Prof Marcel ter Brake ( Chair, ICEC Board), Prof. Wilfried Goldacker (Chair, ICMC board), Dr. D Kanjilal (Director IUAC), Dr R K Bhandari, (President, Indian Cryogenic Council ). Dr. T S Datta, Chair Local Organizing Committee coordinated the proceedings of the inaugural function. 3. Technical

Internal accounting system for feed materials in the plutonium fuel fabrication complex at Cadarache

International Nuclear Information System (INIS)

Arnal, T.; Guillet, H.

1976-01-01

The internal accounting system of the Fabrication and Radiometallurgical Inspection Service (SFER) is basically designed to meet national and international requirements for nuclear materials accountancy as applied to feed materials. The authors discuss the principles underlying this accounting system for the case of the Plutonium Fuel Assembly Fabrication Complex at Cadarache. The sphere of application of the system covers more than 200 work stations and approximately 100 different materials. Some 20000 movements of feed materials per year represent transfers of a cumulative mass much greater than one ton of fissile material. A data processing system has therefore become essential in order to ensure the rapid and reliable acquisition of accounting data relating to these movements. The authors describe the system (definition of stations and material codes, description of supporting facilities used) and discuss the mode of acquisition with particular reference to relative speed of action. In conclusion, the authors indicate that the system offers interesting possibilities, in addition to its original purpose, in the following areas: Preparation of material balances; compliance with safety regulations to avert the risk of criticality; discouragement of possible diversion. (author)

Mapping residual and internal stress in materials by neutron diffraction

International Nuclear Information System (INIS)

Withers, Ph.J.

2007-01-01

Neutron diffraction provides one of the few means of mapping residual stresses deep within the bulk of materials and components. This article reviews the basic scientific methodology by which internal strains and stresses are inferred from recorded diffraction peaks. Both conventional angular scans and time-of-flight measurements are reviewed and compared. Their complementarity with analogous synchrotron X-ray methods is also highlighted. For measurements to be exploited in structural integrity calculations underpinning the safe operation of engineering components, measurement standards have been defined and the major findings are summarised. Examples are used to highlight the unique capabilities of the method showing how it can provide insights ranging from the basic physics of slip mechanisms in hexagonal polycrystalline materials, through the materials optimisation of stress induced transformations in smart nano-materials, to the industrial introduction of novel friction welding processes exploiting stress residual measurements transferred from prototype sub-scale tests to the joining of full-scale aero-engine assemblies. (author)

ROCAM: The 5-th International Edition of Romanian Conference on Advanced Materials. Abstracts

International Nuclear Information System (INIS)

Stanculescu, Florin

2006-01-01

The proceedings of the 5-th International Edition of Romanian Conference on Advanced Materials and Crystal Growth with special topics on nano and multifunctional materials held on September 11-14, 2006 in Bucharest- Magurele, Romania, contains contributions presented as plenary lectures, invited papers and regular contributions in eight sections, namely: 1. Growth and characterization of inorganic crystals; 2. Growth and characterization of organic and biological crystals; 3. Nano and microstructured materials and thin films; 4. Polymers/fuel cells and hydrogen storage; 5. Plasma deposition and applications; 6. Advanced processing and characterization / noncrystalline solids; 7. Advanced nuclear materials; 8. Advanced materials: general aspects

A Quantitative Property-Property Relationship for the Internal Diffusion Coefficients of Organic Compounds in Solid Materials

DEFF Research Database (Denmark)

Huang, Lei; Fantke, Peter; Jolliet, Olivier

2017-01-01

of chemical-material combinations. This paper develops and evaluates a quantitative property-property relationship (QPPR) to predict diffusion coefficients for a wide range of organic chemicals and materials. We first compiled a training dataset of 1103 measured diffusion coefficients for 158 chemicals in 32......Indoor releases of organic chemicals encapsulated in solid materials are major contributors to human exposures and are directly related to the internal diffusion coefficient in solid materials. Existing correlations to estimate the diffusion coefficient are only valid for a limited number...... consolidated material types. Following a detailed analysis of the temperature influence, we developed a multiple linear regression model to predict diffusion coefficients as a function of chemical molecular weight (MW), temperature, and material type (adjusted R2 of 0.93). The internal validations showed...

FOREWORD International Conference on Defects in Insulating Materials

Science.gov (United States)

Valerio, Mário Ernesto Giroldo; Jackson, R. A.

2010-11-01

These proceedings represent a sample of the scientific works presented during ICDIM2008, the 16th International Conference on Defects in Insulating Materials, held at the Federal University of Sergipe, Aracaju, Brazil from 24-29 August 2008. The conference was the latest in a series which began at Argonne in 1956, and which has been held most recently in Riga, Latvia (2004) and Johannesburg, South Africa (2000). The conference was also related scientifically to the EURODIM series, which have been held most recently in Milan, Italy (2006), Wroclaw, Poland (2002) and Pecs, Hungary (2010). The aim of the conference was to bring together physicists, chemists and materials scientist to discuss defects in insulating materials and their effect on materials, including their optical, mass/charge transport, energy storage and sensor properties. The conference featured 6 plenary lectures, 60 contributed lectures and about 130 posters. The posters were displayed for the whole conference, but discussed in two three-hour sessions. We are grateful to the International Advisory Committee for suggesting invited speakers and to the Programme Committee for their help in refereeing all the abstracts and choosing the contributed oral contributions. We would also like to thank the Local Organising Committee and the Brazilian Physical Society for their help with local organisation and the online registration/payment process respectively. The chairpersons would like to specially thanks all the sponsors listed below for financial support. The Federal University of Sergipe, one of the public and 'free tuition' Universities of the Country, run by the Brazilian Ministry of Education, were pleased to host this 16th meeting, the first one in Latin America. Mario E G Valerio Conference Chair Robert A Jackson Programme Chair Conference Scope Scope of the Conference was the presentation of the latest investigations on point and extended defects in bulk materials and thin films. Technological

RILEM International Symposium on Materials and Joints in Timber Structures

CERN Document Server

Reinhardt, H-W; Garrecht, Harald

2014-01-01

This book contains the contributions from the RILEM International Symposium on Materials and Joints in Timber Structures that was held in Stuttgart, Germany from October 8 to 10, 2013. It covers recent developments in the materials and the joints used in modern timber structures. Regarding basic wooden materials, the contributions highlight the widened spectrum of products comprising cross-laminated timber, glulam and LVL from hardwoods and block glued elements. Timber concrete compounds, cement bonded wood composites and innovative light-weight constructions represent increasingly employed alternatives for floors, bridges and facades. With regard to jointing technologies, considerable advances in both mechanical connections and glued joints are presented. Self-tapping screws have created unprecedented options for reliable, strong as well as ductile joints and reinforcement technologies. Regarding adhesives, which constitute the basis of the jointing/laminating technology of modern timber products, extended o...

FOREWORD: 13th International Workshop on Plasma-Facing Materials and Components for Fusion Applications/1st International Conference on Fusion Energy Materials Science 13th International Workshop on Plasma-Facing Materials and Components for Fusion Applications/1st International Conference on Fusion Energy Materials Science

Science.gov (United States)

Jacob, Wolfgang; Linsmeier, Christian; Rubel, Marek

2011-12-01

The 13th International Workshop on Plasma-Facing Materials and Components (PFMC-13) jointly organized with the 1st International Conference on Fusion Energy Materials Science (FEMaS-1) was held in Rosenheim (Germany) on 9-13 May 2011. PFMC-13 is a successor of the International Workshop on Carbon Materials for Fusion Applications series. Between 1985 and 2003 ten 'Carbon Workshops' were organized in Jülich, Stockholm and Hohenkammer. Then it was time for a change and redefinition of the scope of the symposium to reflect the new requirements of ITER and the ongoing evolution in the field. Under the new name (PFMC-11), the workshop was first organized in 2006 in Greifswald, Germany and PFMC-12 took place in Jülich in 2009. Initially starting in 1985 with about 40 participants as a 1.5 day workshop, the event has continuously grown to about 220 participants at PFMC-12. Due to the joint organization with FEMaS-1, PFMC-13 set a new record with more than 280 participants. The European project Fusion Energy Materials Science, FEMaS, coordinated by the Max-Planck-Institut für Plasmaphysik (IPP), organizes and stimulates cooperative research activities which involve large-scale research facilities as well as other top-level materials characterization laboratories. Five different fields are addressed: benchmarking experiments for radiation damage modelling, the application of micro-mechanical characterization methods, synchrotron and neutron radiation-based techniques and advanced nanoscopic analysis based on transmission electron microscopy. All these fields need to be exploited further by the fusion materials community for timely materials solutions for a DEMO reactor. In order to integrate these materials research fields, FEMaS acted as a co-organizer for the 2011 workshop and successfully introduced a number of participants from research labs and universities into the PFMC community. Plasma-facing materials experience particularly hostile conditions as they are

Transport of radioactive material. 1994-2002. International Atomic Energy Agency publications

International Nuclear Information System (INIS)

2002-10-01

This document lists all sales publications, IAEA-TECDOC Series, Training Course Series and National Competent Authorities Lists of the International Atomic Energy Agency dealing with the transport of radioactive materials during the period 1994-2002. It gives a short abstract and contents of these issues along with their costs in EURO

International collaboration in the development of materials for fusion

International Nuclear Information System (INIS)

Amelinckx, S.

1988-01-01

International collaboration in the field of fusion physics research has become a tradition since many years. There are good reasons for this. Fusion physics experiments require progressively larger and more expensive machines. The construction of a major fusion device is beyond the possibility of single nations, except for the largest ones. Moreover it is desirable to test several fundamentally different design options. It would therefore be unreasonable to duplicate major fusion physics experiments. The necessity to pool and coordinate efforts in this area has therefore been recognized since many years and not only within the European community, but even on a global scale. The situation is somewhat different in the area of fusion materials research. In a number of areas of materials research 'big machines' are not required and meaningful research is within the reach of even small countries, moreover it can be done in decentralized fashion. It should nevertheless be noted that the number of properties to be studied and the number of materials options to be evaluated is so extensive that even here excessive duplication would be harmful. (orig.)

Irradiation experiments on materials for core internals, pressure vessel and fuel cladding

Energy Technology Data Exchange (ETDEWEB)

Tsukada, Takashi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1998-03-01

Materials degradation due to the aging phenomena is one of the key issues for the life assessment and extension of the light water reactors (LWRs). This presentation introduces JAERI`s activities in the field of LWR material researches which utilize the research and testing reactors for irradiation experiments. The activities are including the material studies for the core internals, pressure vessel and fuel cladding. These materials are exposed to the neutron/gamma radiation and high temperature water environments so that it is worth reviewing their degradation phenomena as the continuum. Three topics are presented; For the core internal materials, the irradiation assisted stress corrosion cracking (IASCC) of austenitic stainless steels is the present major concern. At JAERI the effects of alloying elements on IASCC have been investigated through the post-irradiation stress corrosion cracking tests in high-temperature water. The radiation embrittlement of pressure vessel steels is still a significant issue for LWR safety, and at JAERI some factors affecting the embrittlement behavior such as a dose rate have been investigated. Waterside corrosion of Zircaloy fuel cladding is one of the limiting factors in fuel rod performance and an in-situ measurement of the corrosion rate in high-temperature water was performed in JMTR. To improve the reliability of experiments and to extent the applicability of experimental techniques, a mutual utilization of the technical achievements in those irradiation experiments is desired. (author)

The REEME project: a cooperative model for sharing international medical education materials.

Science.gov (United States)

Iserson, Kenneth V

2008-07-01

Although the Internet has become an excellent source of medical education materials, in many specialties, including Emergency Medicine (EM), most of the information is in English. Few international EM practitioners can attend costly specialty conferences, importing foreign experts to teach at these conferences is costly and, even then, these experts are available for a limited time to relatively few people. Countries with minimal health care or medical education budgets find providing even basic materials for professional medical education difficult. An exciting international project now freely distributes Spanish language educational programs to health care professionals on topics relating to EM. The Recursos Educacionales en Español para Medicina de Emergencia (REEME; Educational Resources in Spanish for EM) Project (www.reeme.arizona.edu) was developed to overcome some of these problems by providing language-specific specialty information and widespread international availability, and by promoting international cooperation among professional health care educators. It also provides a ready source of Spanish medical vocabulary for those trying to learn the language. With computer support from the University of Arizona's Learning and Technology Center, REEME first went "live" on November 1, 2004. Three years later, as of November 1, 2007, the site had 575 programs from 411 donors representing 19 countries and the United Nations. There are currently about 645 downloads per month to users in 73 countries. The REEME Project demonstrates the power of the Internet as a means to achieve international cooperation in medical education, and can serve as a model for similar projects in other specialties and languages.

Safe Transport of Radioactive Material, International Regulations and its Supporting Documents

International Nuclear Information System (INIS)

El-Shinawy, R.M.K.

2005-01-01

Safe transport of radioactive material regulations issued by IAEA since 1961, provide standards for insuring a high level of safety of people,transport workers, property and environment against radiation, contamination and criticality hazards as well as thermal effects associated with the transport of the radioactive wastes and material. The history ,development, philosophy and scope of these international regulations were mentioned as well as the different supporting documents to the regulations for safe transport of radioactive material were identified.The first supporting document , namely TS - G-1.1 ( ST-2) ,Advisory material is also issued by the IAEA.It contains both the advisory and explanatory materials previously published in safety series No 7 and 37 and therefore TS-G-1.1 (ST-2) will supersede safety series No 7 and 37. The second supporting document namely TS-G-1.2 (ST-3), planning and preparing for emergency response to transport accidents involving radioactive material ,which will supersede safety series No 87. In addition to quality assurance (SS=113), compliance assurance (SS=112), the training manual and other

Safe Transport of Radioactive Material, International Regulations and its Supporting Documents

Energy Technology Data Exchange (ETDEWEB)

El-Shinawy, R M.K. [Radiation Protection Dept., NRC, Atomic Energy Authority, Cairo (Egypt)

2005-04-01

Safe transport of radioactive material regulations issued by IAEA since 1961, provide standards for insuring a high level of safety of people,transport workers, property and environment against radiation, contamination and criticality hazards as well as thermal effects associated with the transport of the radioactive wastes and material. The history ,development, philosophy and scope of these international regulations were mentioned as well as the different supporting documents to the regulations for safe transport of radioactive material were identified.The first supporting document , namely TS - G-1.1 ( ST-2) ,Advisory material is also issued by the IAEA.It contains both the advisory and explanatory materials previously published in safety series No 7 and 37 and therefore TS-G-1.1 (ST-2) will supersede safety series No 7 and 37. The second supporting document namely TS-G-1.2 (ST-3), planning and preparing for emergency response to transport accidents involving radioactive material ,which will supersede safety series No 87. In addition to quality assurance (SS=113), compliance assurance (SS=112), the training manual and other.

ic-cmtp3: 3rd International Conference on Competitive Materials and Technology Processes

Science.gov (United States)

2016-04-01

Competitiveness is one of the most important factors in our lives and it plays a key role in the efficiency both of organizations and societies. The more scientifically advanced and prepared organizations develop more competitive materials with better physical, chemical, and biological properties, and the leading companies apply more competitive equipment and technological processes. The aims of the 3rd International Conference on Competitive Materials and Technology Processes (ic-cmtp3), and the 1st International Symposium on Innovative Carbons and Carbon Based Materials (is-icbm1) and the 1st International Symposium on Innovative Construction Materials (is-icm1) organized alongside are the following: —Promote new methods and results of scientific research in the fields of material, biological, environmental and technological sciences; —Exchange information between the theoretical and applied sciences as well as technical and technological implementations; —Promote communication and collaboration between the scientists, researchers and engineers of different nations, countries and continents. Among the major fields of interest are advanced and innovative materials with competitive characteristics, including mechanical, physical, chemical, biological, medical and thermal, properties and extreme dynamic strength. Their crystalline, nano - and micro-structures, phase transformations as well as details of their technological processes, tests and measurements are also in the focus of the ic-cmtp3 conference and the is-scbm1 and is-icm1 symposia. Multidisciplinary applications of material science and the technological problems encountered in sectors like ceramics, glasses, thin films, aerospace, automotive and marine industries, electronics, energy, construction materials, medicine, biosciences and environmental sciences are of particular interest. In accordance with the program of the ic-cmtp3 conference and is-icbm1 and is-icm1 symposia we have received more

Development of a Method to Assess the Radiation Dose due to Internal Exposure to Short-lived Radioactive Materials

International Nuclear Information System (INIS)

Benmaman, D.; Koch, J.; Ribak, J.

2014-01-01

Work with radioactive materials requires monitoring of the employees' exposure to ionizing radiation. Employees may be exposed to radiation from internal and/or external exposure. Control of external exposure is mostly conducted through personal radiation dosimeters provided to employees. Control of internal exposure can be performed by measuring the concentration of radioactive substances excreted in urine or through whole-body counting in which the entire body or target organs are scanned with a sensitive detector system (1). According to the regulations in Israel an employee that may be internally exposed must undergo an exposure control at least once every three months. The idea lying behind the control of internal exposure by urine testing is that if radioactive material has penetrated into the employee body, it can be detected even if the test is performed once every three months. A model was fitted for each element describing its dispersion in the body and its excretion therefrom (2). By means of this model, one can estimate the activity that entered the body and calculate the resulting radiation dose to which the worker was exposed. There is a problem to implement this method when it comes to short-lived radioactive materials, for which it is very likely that the material that penetrated into the body has decayed and cannot be detected by testing once every three months. As a result, workers with short-lived radioactive materials are presently not monitored for internal exposure, in contradiction to the requirements of the Safety at Work Regulations. The purpose of the study is to develop an alternative method to assess the amount of radioactive material absorbed in the body and the resulting radiation dose due to internal exposure of workers to short-lived radioactive materials

U.S. Materials Science on the International Space Station: Status and Plans

Science.gov (United States)

Chiaramonte, Francis P.; Kelton, Kenneth F.; Matson, Douglas M.; Poirier, David R.; Trivedi, Rohit K.; Su, Ching-Hua; Volz, Martin P.; Voorhees, Peter W.

2010-01-01

This viewgraph presentation reviews the current status and NASA plans for materials science on the International Space Station. The contents include: 1) Investigations Launched in 2009; 2) DECLIC in an EXPRESS rack; 3) Dynamical Selection of Three-Dimensional Interface Patterns in Directional Solidification (DSIP); 4) Materials Science Research Rack (MSRR); 5) Materials Science Laboratory; 6) Comparison of Structure and Segregation in Alloys Directionally Solidified in Terrestrial and Microgravity Environments (MICAST/CETSOL); 7) Coarsening in Solid Liquid Mixtures 2 Reflight (CSLM 2R); 8) Crystal Growth Investigations; 9) Levitator Investigations; 10) Quasi Crystalline Undercooled Alloys for Space Investigation (QUASI); 11) The Role of Convection and Growth Competition in Phase Selection in Microgravity (LODESTARS); 12) Planned Additional Investigations; 13) SETA; 14) METCOMP; and 15) Materials Science NRA.

International Materials Research Meeting in the Greater Region: “Current Trends in the Characterisation of Materials and Surface Modification”

Science.gov (United States)

2017-10-01

Preface Dear ladies and gentlemen, On 6th and 7th of April 2017 took place the “International Materials Research Meeting in the Greater Region” at the Saarland University, Saarbrücken, Germany. This meeting corresponded to the 9th EEIGM International Conference on Advanced Materials Research and it was intended as a meeting place for researchers of the Greater Region as well as their partners of the different cooperation activities, like the EEIGM program, the ‘Erasmus Mundus’ Advanced Materials Science and Engineering Master program (AMASE), the ‘Erasmus Mundus’ Doctoral Program in Materials Science and Engineering (DocMASE) and the CREATe-Network. On this meeting, 72 participants from 15 countries and 24 institutions discussed and exchanged ideas on the latest trends in the characterization of materials and surface modifications. Different aspects of the material research of metals, ceramics, polymers and biomaterials were presented. As a conclusion of the meeting, the new astronaut of the European Space Agency Dr. Matthias Maurer, who is an alumni of the Saarland University and the EEIGM, held an exciting presentation about his activities. Following the publication of selected papers of the 2009 meeting in Volume 5 and 2012 meeting in Volume 31 of this journal, it is a great pleasure to present this selection of 9 articles to the readers of the IOP Conference Series: Materials Science and Engineering. The editors are thankful to all of the reviewers for reviewing the papers. Special praise is also given to the sponsors of the conference: European Commission within the program Erasmus Mundus (AMASE and DocMASE), Erasmus+ (AMASE), and Horizon2020 (CREATe-Network, Grant agreement No 644013): the DAAD (Alumni Program), and the German-French University (PhD-Track). List of Author signatures, Conference topics, Organization, Conference impressions and list of the participants are available in this PDF.

Status and possible prospects of an international fusion materials irradiation facility

International Nuclear Information System (INIS)

Cozzani, F.

1999-01-01

Structural materials for future DT fusion power reactors will have to operate under intense neutron fields with energies up to 14 MeV and fluences in the order of 2 MW/m 2 per year. As environmental acceptability, safety considerations and economic viability will be ultimately the keys to the widespread introduction of fusion power, the development of radiation-resistant and low activation materials would contribute significantly to fusion development. For this purpose, testing of materials under irradiation conditions close to those expected in a fusion power station would require the availability, in an appropriate time framework, of an intense, high-energy neutron source. Recent advances in linear accelerator technology, in small specimens testing technology, and in the comprehension of damage phenomena, lead to the conclusion that an accelerator-based D-Li neutron source, with beam energy variability, would provide the most realistic option for a fusion materials testing facility. Under the auspices of the IEA, an international effort (EU, Japan, US, RF) to carry out the conceptual design activities (CDA) of an international fusion materials irradiation facility (IFMIF), based on the D-Li concept, have been carried out successfully. A final conceptual design report was produced at the end of 1996. A phase of conceptual design evaluation (CDE), presently underway, is extending and further refining some of the conceptual design details of IFMIF. The results indicate that an IFMIF-class installation would be technically feasible and could meet its mission objectives. However, a suitable phase of Engineering Validation, to carry out some complementary R and D and prototyping, would still be needed to resolve a few key technical uncertainties before the possibility to proceed toward detailed design and construction could be explored. (orig.)

9th International Frumkin symposium: Electrochemical technologies and materials for 21st century. Abstracts

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-07-01

Abstracts of the 9th International Frumkin symposium: Electrochemical technologies and materials for 21st century are presented. The symposium was held 24-29 October 2010 in Moscow. The symposium included the following microsymposiums: Electrical double layer and electrochemical kinetics (from phenomenological to molecular level); New processes, materials and devices for successful electrochemical transformation of energy; Corrosion and protection of materials; General and local corrosion; Electroactive composition materials; Bioelectrochemistry. The Frumkin symposium includes plenary lectures, oral and poster presentations. Official language of the symposium is English

9th International Frumkin symposium: Electrochemical technologies and materials for 21st century. Abstracts

International Nuclear Information System (INIS)

2010-01-01

Abstracts of the 9th International Frumkin symposium: Electrochemical technologies and materials for 21st century are presented. The symposium was held 24-29 October 2010 in Moscow. The symposium included the following microsymposiums: Electrical double layer and electrochemical kinetics (from phenomenological to molecular level); New processes, materials and devices for successful electrochemical transformation of energy; Corrosion and protection of materials; General and local corrosion; Electroactive composition materials; Bioelectrochemistry. The Frumkin symposium includes plenary lectures, oral and poster presentations. Official language of the symposium is English [ru

Proceedings of the international conference on molecular spectroscopy of advanced materials and biomolecules

International Nuclear Information System (INIS)

Sajan, D.

2012-01-01

This conference was an effort towards exploring advanced applications, with emphasis on recent trends in the Infrared and Raman spectra of advanced materials and biomolecules. The conference topics focused on a wide range of molecular spectroscopy, yet connected with molecular biological systems and materials. As molecular spectroscopy is finding tremendous significance in various fields of materials science, biomedical, pharmaceutical, planetary, mineral and forensic sciences, IMSAB 2012, provided a very dynamic and interactive platform for the international scientific community specializing in the field. Papers relevant to INIS are indexed separately

VII International scientific conference Radiation-thermal effects and processes in inorganic materials. Proceedings

International Nuclear Information System (INIS)

2010-01-01

In the collection there are the reports of the VII International scientific conference and the VII All-Russian school-conference Radiation-thermal effects and processes in inorganic materials which were conducted on October 2-10, 2010, in Tomsk. The reports deal with new developments of charged particles high-intensity beam sources, high-temperature metrology of high-current beams and work materials, radiation-thermal stimulated effects and processes in inorganic materials, physical basics of technological processes, radiation-thermal technologies and equipment for their realization, allied branches of science and technology, specifically, nanotechnologies [ru

Materials Science Research Rack Onboard the International Space Station

Science.gov (United States)

Reagan, Shawn; Frazier, Natalie; Lehman, John

2016-01-01

The Materials Science Research Rack (MSRR) is a research facility developed under a cooperative research agreement between NASA and ESA for materials science investigations on the International Space Station (ISS). MSRR was launched on STS-128 in August 2009 and currently resides in the U.S. Destiny Laboratory Module. Since that time, MSRR has logged more than 1400 hours of operating time. The MSRR accommodates advanced investigations in the microgravity environment on the ISS for basic materials science research in areas such as solidification of metals and alloys. The purpose is to advance the scientific understanding of materials processing as affected by microgravity and to gain insight into the physical behavior of materials processing. MSRR allows for the study of a variety of materials, including metals, ceramics, semiconductor crystals, and glasses. Materials science research benefits from the microgravity environment of space, where the researcher can better isolate chemical and thermal properties of materials from the effects of gravity. With this knowledge, reliable predictions can be made about the conditions required on Earth to achieve improved materials. MSRR is a highly automated facility with a modular design capable of supporting multiple types of investigations. The NASA-provided Rack Support Subsystem provides services (power, thermal control, vacuum access, and command and data handling) to the ESA-developed Materials Science Laboratory (MSL) that accommodates interchangeable Furnace Inserts (FI). Two ESA-developed FIs are presently available on the ISS: the Low Gradient Furnace (LGF) and the Solidification and Quenching Furnace (SQF). Sample Cartridge Assemblies (SCAs), each containing one or more material samples, are installed in the FI by the crew and can be processed at temperatures up to 1400?C. ESA continues to develop samples with 14 planned for launch and processing in the near future. Additionally NASA has begun developing SCAs to

Staged deployment of the International Fusion Materials Irradiation Facility

International Nuclear Information System (INIS)

Takeuchi, H.; Sugimoto, M.; Nakamura, H.

2001-01-01

The International Fusion Materials Irradiation Facility (IFMIF) employs an accelerator based D-Li intense neutron source as defined in the 1995-96 Conceptual Design Activity (CDA) study. In 1999, IEA mandated a review of the CDA IFMIF design for cost reduction without change to its original mission. This objective was accomplished by eliminating the previously assumed possibility of potential upgrade of IFMIF beyond the user requirements. The total estimated cost was reduced from $797.2 M to $487.8 M. An option of deployment in 3 stages was also examined to reduce the initial investment and annual expenditures during construction. In this scenario, full performance is achieved gradually with each interim stage as follows. 1st Stage: 20% operation for material selection for ITER breeding blanket, 2nd Stage: 50% operation to demonstrate materials performance of a reference alloy for DEMO, 3rd Stage: full performance operation ( 2MW/m 2 at 500cm 3 ) to obtain engineering data for potential DEMO materials under irradiation up to 100-200 dpa. In summary, the new, reduced cost IFMIF design and staged deployment still satisfies the original mission. The estimated cost of the 1st Stage facility is only $303.6 M making it financially much more attractive. Currently, IFMIF Key Element Technology Phase (KEP) is underway to reduce the key technology risk factors. (author)

1. international spring school and symposium on advances in materials science; contributed papers. Proceedings. V.2

International Nuclear Information System (INIS)

1994-03-01

The first International Conference on Advances in Materials Science was held on 15-20 March, 1994 in Cairo. The specialists discussed advances in materials science formation, development and observation. The applications of materials science technique in the field of construction material, Moessbauer measurements, physico science, corrosion and mechanical alloying were discussed at the meeting. more than 700 papers were presented in the meeting

1. international spring school and symposium on advances in materials science; contributed papers. Proceedings. V.2

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-03-01

The first International Conference on Advances in Materials Science was held on 15-20 March, 1994 in Cairo. The specialists discussed advances in materials science formation, development and observation. The applications of materials science technique in the field of construction material, Moessbauer measurements, physico science, corrosion and mechanical alloying were discussed at the meeting. more than 700 papers were presented in the meeting.

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

Energy Technology Data Exchange (ETDEWEB)

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

2011-07-01

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

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

International Nuclear Information System (INIS)

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

2011-01-01

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

PREFACE: International Conference on Advanced Structural and Functional Materials Design 2008

Science.gov (United States)

Kakeshita, Tomoyuki

2009-07-01

The Ministry of Education, Culture, Sports, Science and Technology of Japan started the Priority Assistance for the Formation of Worldwide Renowned Centers of Research - Global COE Program. This program is based on the competitive principle where a third party evaluation decides which program to support and to give priority support to the formation of world-class centers of research. Our program Center of Excellence for Advanced Structural and Functional Materials Design was selected as one of 13 programs in the field of Chemistry and Materials Science. This center is composed of two materials-related Departments in the Graduate School of Engineering: Materials and Manufacturing Science and Adaptive Machine Systems, and 4 Research Institutes: Center for Atomic and Molecular Technologies, Welding and Joining Research Institute, Institute of Scientific and Industrial Research and Research Center for Ultra-High Voltage Electron Microscopy. Recently, materials research, particularly that of metallic materials, has specialized only in individual elemental characteristics and narrow specialty fields, and there is a feeling that the original role of materials research has been forgotten. The 6 educational and research organizations which make up the COE program cooperatively try to develop new advanced structural and functional materials and achieve technological breakthrough for their fabrication processes from electronic, atomic, microstructural and morphological standpoints, focusing on their design and application: development of high performance structural materials such as space plane and turbine blades operating under a severe environment, new fabrication and assembling methods for electronic devices, development of evaluation technique for materials reliability, and development of new biomaterials for regeneration of biological hard tissues. The aim of this international conference was to report the scientific progress in our Global COE program and also to discuss

International dimension of illicit trafficking in nuclear and other radioactive material

International Nuclear Information System (INIS)

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

2002-01-01

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

An Analysis of U.S. Business Schools' Catalogs, Application Packages, and Program Materials from an International Perspective.

Science.gov (United States)

Webb, Marion S.; Mayer, Kenneth R.; Pioche, Virginie

1999-01-01

Catalogs, application packages, and program materials from 106 business schools were analyzed to determine the degree of international coverage in business schools' curricula. Findings indicated a trend to require international functional courses, such as international finance, in the traditional Master in business administration programs and to…

Materiality in Public Sector Financial Audit: International Practice and the Opinion of Brazilian Experts

Directory of Open Access Journals (Sweden)

Juliane Madeira Leitão

2016-04-01

Full Text Available Materiality in private sector financial audit is a topic that has been relatively well developed in the literature. Specific research in this regard in public sector auditing, on the other hand, is scarce at the international level and absent in Brazil. In view of this, the purpose of this study was to identify the parameters used to determine materiality in public sector financial audit. To this end, we sent questionnaires to the 192 Supreme Audit Institutions that are members of INTOSAI and to 36 Brazilian public auditors, specialists in financial audit, who are staff members of the TCU or the CGU seeking information with respect to the Institutions’ guidelines and the auditors’ perceptions about materiality. Results reveal that expenditures, revenues and total assets are the benchmarks most recommended by respondents for defining materiality in the public sector. In addition, they recommended the adoption of percentages of up to 2% for each of these parameters in defining what is material. It was observed, as well, especially with respect to the effectiveness of internal control and to public expectations or interests, that qualitative aspects should be also taken into account in determining materiality, although a lesser degree of importance is attributed to this than to the quantitative aspects,. The study contributes to the accounting literature on the development of audits, particularly with respect to the use of a concept, materiality, that is always emphasized in professional standards, but about which there are few objective guidelines.

Materials Science Research Hardware for Application on the International Space Station: an Overview of Typical Hardware Requirements and Features

Science.gov (United States)

Schaefer, D. A.; Cobb, S.; Fiske, M. R.; Srinivas, R.

2000-01-01

NASA's Marshall Space Flight Center (MSFC) is the lead center for Materials Science Microgravity Research. The Materials Science Research Facility (MSRF) is a key development effort underway at MSFC. The MSRF will be the primary facility for microgravity materials science research on board the International Space Station (ISS) and will implement the NASA Materials Science Microgravity Research Program. It will operate in the U.S. Laboratory Module and support U. S. Microgravity Materials Science Investigations. This facility is being designed to maintain the momentum of the U.S. role in microgravity materials science and support NASA's Human Exploration and Development of Space (HEDS) Enterprise goals and objectives for Materials Science. The MSRF as currently envisioned will consist of three Materials Science Research Racks (MSRR), which will be deployed to the International Space Station (ISS) in phases, Each rack is being designed to accommodate various Experiment Modules, which comprise processing facilities for peer selected Materials Science experiments. Phased deployment will enable early opportunities for the U.S. and International Partners, and support the timely incorporation of technology updates to the Experiment Modules and sensor devices.

17th International Conference on Textures of Materials (ICOTOM 17)

International Nuclear Information System (INIS)

Skrotzki, Werner; Oertel, Carl-Georg

2015-01-01

The 17th International Conference on Textures of Materials (ICOTOM 17) took place in Dresden, Germany, August 24-29, 2014. It belongs to the 'triennial' series of ICOTOM meetings with a long tradition, starting in 1969 - Clausthal, 1971 - Cracow, 1973 - Pont-à-Mousson, 1975 - Cambridge, 1978 - Aachen, 1981 - Tokyo, 1984 - Noordwijkerhout, 1987 - Santa Fe, 1990 - Avignon, 1993 - Clausthal, 1996 - Xian, 1999 - Montreal, 2002 - Seoul, 2005 - Leuven, 2008 - Pittsburgh, 2011 - Mumbai, 2014 - Dresden. ICOTOM 17 was hosted by the Dresden University of Technology, Institute of Structural Physics. Following the tradition of the ICOTOM conferences, the main focus of ICOTOM-17 was to promote and strengthen the fundamental understanding of the basic processes that govern the formation of texture and its relation to the properties of polycrystalline materials. Nonetheless, it was the aim to forge links between basic research on model materials and applied research on engineering materials of technical importance. Thus, ICOTOM 17 provided a forum for the presentation and discussion of recent progress in research of texture and related anisotropy of mechanical and functional properties of all kinds of polycrystalline materials including natural materials like rocks. Particular attention was paid to recent advances in texture measurement and analysis as well as modeling of texture development for all kinds of processes like solidification, plastic deformation, recrystallization and grain growth, phase transformations, thin film deposition, etc. Hence, ICOTOM 17 was of great interest to materials scientists, engineers from many different areas and geoscientists. The topics covered by ICOTOM 17 were: 1. Mathematical, numerical and statistical methods of texture analysis 2. Deformation textures 3. Crystallization, recrystallization and growth textures 4. Transformation textures 5. Textures in functional materials 6. Textures in advanced materials 7. Textures in rocks 8

Fifth international symposium on the packaging and transportation of radioactive materials

International Nuclear Information System (INIS)

Allen, G.C. Jr.; Kent, D.C.; Pope, R.B.

1980-01-01

This article is a brief review of the Fifth Interantional Symposium on the Packaging and Transportation of Radioactive Materials held at Las Vegas, Nev., May 7-12, 1978. This symposium was sponsored by Sandia Laboratories under the auspices of the Department of Energy. Highlighting the meeting were papers on regulations, legal issues, logistics and planning, risk assessment, ad various technology- and systems-related topics. It is apparent that, although transportation of radioactive materials has received much attention in the past, even more attention will be required in the future or transportation may become a limiting factor in the nuclear power option. Areas requiring special attention include: (1) the continued evaluation and updating of regulations and the coordination of this effort on an international level; (2) the use of risk analysis not only to establish, modify, or verify regulations but also to lend credence to the regulations in the public view; (3) the development of technology to provide cost-effective and more easily used packaging and transportation systems; (4) the expansion of effort to provide accurate information to legislative and other rule-making bodies and to the public to aid in making rational decisions relative to transportation; (5) the evaluation of large-scale international transfer of spent fuel; and (6) the commitment to, and fabrication of, the large fleets of shipping systems that will soon be required to transport the growing quantities of spent fuel, nuclear waste, and other radioactive materials

Inspection of the coupling part material degradation. Some experiences and results from SKODA JS related to internals

International Nuclear Information System (INIS)

Brynda, J.

1998-01-01

In this presentation some experiences and results from SKODA JS, related to internals, are reported. Sketches of the construction of WWER 440 RPV and internal's materials, including chemical composition are given. The results of hardness tests on internal parts are reported as well as some changes in the construction of internal parts which were made to improve their crack and fracture properties

Legal Aspects of international cooperation in the physical protection of nuclear facilities and materials

International Nuclear Information System (INIS)

Herron, L.W.

1981-10-01

This paper provides a detailed analysis of developments in the number field having led the IAEA to promote international cooperation in ensuring adequate physical protection of nuclear facilities and materials. This work resulted in the establishment of recommendations and guidelines in this respect and culminated in the development of the 1980 Convention on the Physical Protection of Nuclear Materials. (NEA) [fr

Ion beam deposition system for depositing low defect density extreme ultraviolet mask blanks

Science.gov (United States)

Jindal, V.; Kearney, P.; Sohn, J.; Harris-Jones, J.; John, A.; Godwin, M.; Antohe, A.; Teki, R.; Ma, A.; Goodwin, F.; Weaver, A.; Teora, P.

2012-03-01

Extreme ultraviolet lithography (EUVL) is the leading next-generation lithography (NGL) technology to succeed optical lithography at the 22 nm node and beyond. EUVL requires a low defect density reflective mask blank, which is considered to be one of the top two critical technology gaps for commercialization of the technology. At the SEMATECH Mask Blank Development Center (MBDC), research on defect reduction in EUV mask blanks is being pursued using the Veeco Nexus deposition tool. The defect performance of this tool is one of the factors limiting the availability of defect-free EUVL mask blanks. SEMATECH identified the key components in the ion beam deposition system that is currently impeding the reduction of defect density and the yield of EUV mask blanks. SEMATECH's current research is focused on in-house tool components to reduce their contributions to mask blank defects. SEMATECH is also working closely with the supplier to incorporate this learning into a next-generation deposition tool. This paper will describe requirements for the next-generation tool that are essential to realize low defect density EUV mask blanks. The goal of our work is to enable model-based predictions of defect performance and defect improvement for targeted process improvement and component learning to feed into the new deposition tool design. This paper will also highlight the defect reduction resulting from process improvements and the restrictions inherent in the current tool geometry and components that are an impediment to meeting HVM quality EUV mask blanks will be outlined.

Naturally occurring radioactive materials (NORM IV). Proceedings of an international conference

International Nuclear Information System (INIS)

2005-10-01

Radionuclides of natural origin are ubiquitous in both working and public environments, although their activity concentrations vary considerably. Exposures to natural sources are in most cases not a matter for regulatory concern. However, there are situations where exposures to natural sources may warrant consideration as to whether controls should be applied. One such situation is where the conditions are conducive to the buildup of elevated concentrations of radon in air. Another situation is the mining and/or processing of material where the activity concentrations of radionuclides of natural origin in the material itself, or in any material arising from the process, are significantly elevated - such material has come to be referred to as Naturally Occurring Radioactive Material (NORM). In the past, regulatory attention has been focused mostly on exposures arising from the mining and processing of uranium ores because such activities are part of the nuclear fuel cycle. More recently, attention has been broadened to include exposures from other industrial activities involving NORM, in recognition of the potential for such activities to also give rise to significant exposures of workers and members of the public if not adequately controlled. More and more countries are now including provisions in their national legislation and regulations for the control of exposures to natural sources, and the body of radiological data on such exposures is growing rapidly. This international conference, NORM IV, follows three previous conferences dealing with radon and NORM. The first was held in Amsterdam in 1997, the second in Krefeld, Germany in 1998 (NORM II), and the third in Brussels in 2001 (NORM III). In addition, an International Symposium on Technologically Enhanced Natural Radiation was held in Rio de Janeiro in 1999 - the IAEA was involved in the organization of that symposium, and published the proceedings as IAEA-TECDOC-1271. The main topic addressed at NORM IV was

Photon activation analysis using internal standards: some studies of the analysis of environmental materials

Energy Technology Data Exchange (ETDEWEB)

Masumoto, K; Yagi, M

1986-01-01

The authors report the application of the internal standard method to the simultaneous determination of trace elements in environmental reference materials. The standard soil material used was IAEA CRM Soil-5. The power plant fly ash reference used was NBS SRM-1633a. Fifteen target elements, including As, Ba and Ce, were determined. Internal standards were supplied by six elements, including Na and Mg. Although there were several interfering elements, their effect could be eliminated by utilizing more than one gamma-ray peak and carrying out appropriate corrections. The values determined for most of the target elements were well within the certified range. Measured concentrations were of the orders of 10 to 1000 ..mu..g/g. 6 references, 2 figures, 5 tables.

Grain boundaries of nanocrystalline materials - their widths, compositions, and internal structures

International Nuclear Information System (INIS)

Fultz, B.; Frase, H.N.

2000-01-01

Nanocrystalline materials contain many atoms at and near grain boundaries. Sufficient numbers of Moessbauer probe atoms can be situated in grain boundary environments to make a clear contribution to the measured Moessbauer spectrum. Three types of measurements on nanocrystalline materials are reported here, all using Moessbauer spectrometry in conjunction with X-ray diffractometry, transmission electron microscopy, or small angle neutron scattering. By measuring the fraction of atoms contributing to the grain boundary component in a Moessbauer spectrum, and by knowing the grain size of the material, it is possible to deduce the average width of grain boundaries in metallic alloys. It is found that these widths are approximately 0.5 nm for fcc alloys and slightly larger than 1.0 nm for bcc alloys.Chemical segregation to grain boundaries can be measured by Moessbauer spectrometry, especially in conjunction with small angle neutron scattering. Such measurements on Fe-Cu and Fe 3 Si-Nb were used to study how nanocrystalline materials could be stabilized against grain growth by the segregation of Cu and Nb to grain boundaries. The segregation of Cu to grain boundaries did not stabilize the Fe-Cu alloys against grain growth, since the grain boundaries were found to widen and accept more Cu atoms during annealing. The Nb additions to Fe 3 Si did suppress grain growth, perhaps because of the low mobility of Nb atoms, but also perhaps because Nb atoms altered the chemical ordering in the alloy.The internal structure of grain boundaries in nanocrystalline materials prepared by high-energy ball milling is found to be unstable against internal relaxations at low temperatures. The Moessbauer spectra of the nanocrystalline samples showed changes in the hyperfine fields attributable to movements of grain boundary atoms. In conjunction with SANS measurements, the changes in grain boundary structure induced by cryogenic exposure and annealing at low temperature were found to be

Statement to the International Conference on the Safety of Transport of Radioactive Material. Vienna, 7 July 2003

International Nuclear Information System (INIS)

ElBaradei, M.

2003-01-01

The transport of radioactive material has been subject to regulation for many decades, and the International Atomic Energy Agency, working with its Member States and all relevant international governmental organizations, has played a key role in fostering the establishment of those regulations and providing for their application. First published in 1961, the IAEA's Regulations for the Safe Transport of Radioactive Material are periodically revised to incorporate technical advances, operational experience and the latest radiation protection principles. These Transport Regulations address all categories of radioactive material. Although recommendatory in nature, they constitute the basis for national regulations in many Member States, and generally become mandatory through the legally binding instruments of the relevant modal bodies, such as the International Maritime Organization or the International Civil Aviation Organization. In some cases, these instruments take the form of universal conventions, such as the Convention on International Civil Aviation or the International Convention for the Safety of Life at Sea; in other cases, they take the form of regional agreements, such as the European Agreement Concerning the International Carriage of Dangerous Goods by Road. Overall, there are 21 universal instruments and 22 regional instruments in force that apply, directly or indirectly, to the safe transport of radioactive material. This current worldwide system of regulatory control, while not without shortcomings, has achieved an excellent safety record. Over several decades of transporting radioactive material, there has not been an in-transit accident with serious human health, economic or environmental consequences attributable to the radioactive nature of the transported goods. In recognition of this fact, the United Nations Committee on the Effects of Atomic Radiation has noted these transport activities as having no radiological impact. This excellent record

International transport of uranium materials from China

International Nuclear Information System (INIS)

Xu Chizhi; Long Xiuaowei; Achilles, G.

1993-01-01

An example of international cooperation is given on the transport of frontend materials from China to Europe. With the assistance of NCS, CNEIC entered into discussions and negotiations with COSCO, the national Chinese shipping line in order to make much cheaper sea transport possible. One of the difficulties to overcome was the passage through the Suez canal but CNEIC, NCS and the port authorities were present to assure smooth operation, during the first passage through the canal, CNEIC key personnels had training at the NCS office in Germany in relation to transport regulations and practice on the job. In turn, NCS personnels were introduced into site specific conditions in China by CNEIC. In the meantime, about 150 containers loaded with yellow cake and about 120 cylinders with low enriched UF6 have been smoothly transported by sea from Shanghai through the Suez canal to European ports. (E.Y.)

Non-proliferation through effective international control, with particular reference to peaceful uses of nuclear material as a result of nuclear disarmament and international control of plutonium

International Nuclear Information System (INIS)

Imai, Ryukichi

1993-01-01

The role of nuclear factors in the international political situation has changed. The emphasis is now on the new circumstance of the post cold-war world. Non-proliferation is dealt with through effective international control, with particular reference to peaceful uses of nuclear material as a result of nuclear weapons dismantling and international control of plutonium

Influence of abutment materials on the implant-abutment joint stability in internal conical connection type implant systems

OpenAIRE

Jo, Jae-Young; Yang, Dong-Seok; Huh, Jung-Bo; Heo, Jae-Chan; Yun, Mi-Jung; Jeong, Chang-Mo

2014-01-01

PURPOSE This study evaluated the influence of abutment materials on the stability of the implant-abutment joint in internal conical connection type implant systems. MATERIALS AND METHODS Internal conical connection type implants, cement-retained abutments, and tungsten carbide-coated abutment screws were used. The abutments were fabricated with commercially pure grade 3 titanium (group T3), commercially pure grade 4 titanium (group T4), or Ti-6Al-4V (group TA) (n=5, each). In order to assess ...

Materials International Space Station Experiment (MISSE): Overview, Accomplishments and Future Needs

Science.gov (United States)

deGroh, Kim K.; Jaworske, Donald A.; Pippin, Gary; Jenkins, Philip P.; Walters, Robert J.; Thibeault, Sheila A.; Palusinski, Iwona; Lorentzen, Justin R.

2014-01-01

Materials and devices used on the exterior of spacecraft in low Earth orbit (LEO) are subjected to environmental threats that can cause degradation in material properties, possibly threatening spacecraft mission success. These threats include: atomic oxygen (AO), ultraviolet and x-ray radiation, charged particle radiation, temperature extremes and thermal cycling, micrometeoroid and debris impacts, and contamination. Space environmental threats vary greatly based on spacecraft materials, thicknesses and stress levels, and the mission environment and duration. For more than a decade the Materials International Space Station Experiment (MISSE) has enabled the study of the long duration environmental durability of spacecraft materials in the LEO environment. The overall objective of MISSE is to test the stability and durability of materials and devices in the space environment in order to gain valuable knowledge on the performance of materials in space, as well as to enable lifetime predictions of new materials that may be used in future space flight. MISSE is a series of materials flight experiments, which are attached to the exterior of the International Space Station (ISS). Individual experiments were loaded onto suitcase-like trays, called Passive Experiment Containers (PECs). The PECs were transported to the ISS in the Space Shuttle cargo bay and attached to, and removed from, the ISS during extravehicular activities (EVAs). The PECs were retrieved after one or more years of space exposure and returned to Earth enabling post-flight experiment evaluation. MISSE is a multi-organization project with participants from the National Aeronautics and Space Administration (NASA), the Department of Defense (DoD), industry and academia. MISSE has provided a platform for environmental durability studies for thousands of samples and numerous devices, and it has produced many tangible impacts. Ten PECs (and one smaller tray) have been flown, representing MISSE 1 through MISSE

2016 International Conference on Physics and Mechanics of New Materials and Their Applications

CERN Document Server

Chang, Shun-Hsyung; Jani, Muaffaq

2017-01-01

This book presents 50 selected peer-reviewed reports from the 2016 International Conference on “Physics and Mechanics of New Materials and Their Applications”, PHENMA 2016 (Surabaya, Indonesia, 19–22 July, 2016). The Proceedings are devoted to processing techniques, physics, mechanics, and applications of advanced materials. As such, they examine a wide spectrum of nanostructures, ferroelectric crystals, materials and composites, as well as other promising materials with special properties. They present nanotechnology approaches, modern environmentally friendly piezoelectric and ferromagnetic techniques, and physical and mechanical studies of the structural and physical-mechanical properties of the materials discussed.  Further, a broad range of original mathematical and numerical methods is applied to solve various technological, mechanical and physical problems, which are inte resting for applications. Great attention is devoted to novel devices with high accuracy, longevity and extended possibilitie...

Problems of Chernobyl. Materials of International scientific and practical conference 'Shelter-98'

International Nuclear Information System (INIS)

Klyuchnikov, O.O.

1999-01-01

These transactions contain materials of International Scientific and Practical Conference 'Shelter-98', which was held 27-30 November 1998 in Slavutich. They describe the results of the research work of the specialists from Ukraine, neighborhood and far foreign counties. The results, targeted at solving the problems of converting the Shelter Object into oncologically safe state

PFMC14. 14th international conference on plasma-facing materials and components for fusion applications. Book of abstracts

International Nuclear Information System (INIS)

2013-01-01

The performance of fusion devices and of a future fusion power plant critically depends on the plasma facing materials and components. Resistance to local heat and particle loads, thermo-mechanical properties, as well as the response to neutron damage of the selected materials are critical parameters which need to be understood and tailored from atomistic to component levels. The 14th International Conference on Plasma-Facing Materials and Components for Fusion Applications addresses these issues. Among the topics of the joint conference recent developments and research results in the following fields are addressed: - Tungsten and tungsten alloys - Low-Z materials - Mixed materials - Erosion, redeposition and fuel retention - Materials under extreme thermal loads - Technology and testing of plasma-facing components - Neutron effects in plasma-facing materials - Advanced characterization of materials and components. Selected international speakers present overview lectures and treat detailed aspects of the given topics. Contributed papers to the subjects of the meeting are solicited for oral and poster presentations.

IFMIF (International Fusion Materials Irradiation Facility) key element technology phase interim report

International Nuclear Information System (INIS)

Nakamura, Hiroo; Ida, Mizuho; Sugimoto, Masayoshi; Takeuchi, Hiroshi; Yutani, Toshiaki

2002-03-01

Activities of International Fusion Materials Irradiation Facility (IFMIF) have been performed under an IEA collaboration since 1995. IFMIF is an accelerator-based deuteron (D + )-lithium (Li) neutron source designed to produce an intense neutron field (2 MW/m 2 , 20 dpa/year for Fe) in a volume of 500 cm 3 for testing candidate fusion materials. In 2000, a 3 year Key Element technology Phase (KEP) of IFMIF was started to reduce the key technology risk factors. This interim report summarizes the KEP activities until mid 2001 in the major project work-breakdown areas of accelerator, target, test facilities and design integration. (author)

1. international spring school and symposium on advances in materials science; invited lectures. Proceedings. V.1

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-03-01

The 1 st international conference on advances in materials science was held on 15-20 March, 1994 in cairo. The specialist discussed material science formation, development and observation. The application of advances in material science technique in the field of atomic energy, structure design, microelectronic structure were discussed at the meeting. more than 400 papers were presented in the meeting.

1. international spring school and symposium on advances in materials science; invited lectures. Proceedings. V.1

International Nuclear Information System (INIS)

1994-03-01

The 1 st international conference on advances in materials science was held on 15-20 March, 1994 in cairo. The specialist discussed material science formation, development and observation. The application of advances in material science technique in the field of atomic energy, structure design, microelectronic structure were discussed at the meeting. more than 400 papers were presented in the meeting

Liability problems of international transportation of nuclear material: The Canadian experience

International Nuclear Information System (INIS)

Schwartz, J.A.

1986-01-01

Canadian law in the field of transportation of radioactive materials has largely adopted international standards. Most of the respective laws, however, are as yet untested in court. According to the author it is likely that a broad and liberal interpretation will be given to all of the provisions which entitle injured parties to seek recourse against a transporter who has negligently carried out the duties imposed upon him. (CW) [de

Special Issue: 14th International Symposium on Novel and Nano Materials

Science.gov (United States)

Kim, Woo-Byoung; Choa, Yong-Ho; Ahn, Hyo-Jin; Park, Il-Kyu

2017-09-01

This Special Issue of Applied Surface Science is intended to provide a collection of peer-reviewed contributions presented at the 14th International Symposium on Novel Nano Materials (ISNNM) held in Budapest, Hungary as one of the most beautiful cities in Europe from July 3 to July 8, 2016. All selected papers underwent the regular peer review process as set by the journal of Applied Surface Science and its publisher (Elsevier).

Assessment of the threat from diverted radioactive material and 'orphan sources' - An international comparison

International Nuclear Information System (INIS)

Steinhausler, F.

2001-01-01

Full text: Multiple international activities have been undertaken to contain the trafficking of weapons-usable material in order to reduce the risk from the proliferation of such material. In addition, over the past decade the issue of unintended handling and transport of radioactive material has become increasingly important. Concurrent with the growing number of radioactive sources in industry, medicine, agriculture and research, the probability for losing control over such sources increases as well ('orphan sources'). The potential impact on society and the environment from these two categories of threat has been documented extensively in the literature. In this study representatives from 11 countries in the Americas, Europe and Asia-Pacific formed a network to exchange information concerning nuclear and other radioactive material on the following topic areas: Legislation and regulatory practices for the production, processing, handling, use, holding, storage, transport, import, and export; History of site-specific non-compliance and enforcement actions, as well as punitive actions; National approach for handling the issue of orphan sources; The role of national security forces; Managerial and technical procedures to ensure material inventory control and accountancy; Aspects of physical protection on-site and during transport; Technical/scientific expertise and equipment available at the national level to detect, identify and quantify such material in the field; Level of practical implementation of technical equipment to detect such material at border crossings, airports, railway stations, and mail distribution centres; Cases of seizure of nuclear and contaminated materials, illegal sales and fraud; Training programmes available for preventing, detecting and responding to the loss of control. The results of the analysis show that, despite several international consensus documents and supporting legislation, in several cases major additional efforts are needed

Status of international collaborative efforts on selected ITER materials

International Nuclear Information System (INIS)

Belyakov, V.A.; Fabritsiev, S.A.; Mazul, I.V.; Rowcliffe, A.F.

2000-01-01

The paper presents an overview of the performance of refractory metals, beryllium, and copper alloys, for the international thermonuclear experimental reactor (ITER) high heat flux structures. High temperature brazing, hot isostatic pressing (HIP), friction welding, explosive bonding, and other methods were explored to join copper alloys to 316 stainless steel for first wall and limiter applications. It is concluded that the main material problems for the ITER high heat flux components are: (a) degradation of properties after the manufacturing cycle (especially for Be/Cu and Cu/stainless steel (SS) joints); (b) helium embrittlement of Be, and Cu, and; (c) radiation-induced loss of fracture toughness for Be, W, and Cu alloys

6. International conference on materials science and condensed matter physics. Abstracts

International Nuclear Information System (INIS)

2012-09-01

This book includes abstracts of the communications presented at the 6th International Conference on Materials Science and Condensed Matter Physics. The aim of this event is two-fold. First, it provides a nice opportunity for discussions and the dissemination of the latest results on selected topics in materials science, condensed-matter physics, and electrical methods of materials treatment. On the other hand, this is an occasion for sketching a broad perspective of scientific research and technological developments for the participants through oral and poster presentations. The abstracts presented in the book cover certain issues of modern theoretical and experimental physics and advanced technology, such as crystal growth, doping and implantation, fabrication of solid state structures; defect engineering, methods of fabrication and characterization of nanostructures including nanocomposites, nanowires and nano dots; fullerenes and nano tubes; quantum wells and superlattices; molecular-based materials, meso- and nano electronics; methods of structural and mechanical characterization; optical, transport, magnetic and superconductor properties, non-linear phenomena, size and interface effects; condensed matter theory; modelling of materials and structural properties including low dimensional systems; advanced materials and fabrication processes, device modelling and simulation of structures and elements; optoelectronics and photonics; microsensors and micro electro-mechanical systems; degradation and reliability, advanced technologies of electro-physico-chemical methods and equipment for materials machining, including modification of surfaces; electrophysical technologies of intensification of heat- and mass-transfer; treatment of biological preparations and foodstuff.

2015 International Conference on Physics and Mechanics of New Materials and their Applications

CERN Document Server

Chang, Shun-Hsyung; Topolov, Vitaly

2016-01-01

This proceedings volume presents selected and peer reviewed 50 reports of the 2015 International Conference on “Physics and Mechanics of New Materials and Their Applications” (Azov, Russia, 19-22 May, 2015), devoted to 100th Anniversary of the Southern Federal University, Russia. The book presents processing techniques, physics, mechanics, and applications of advanced materials. The book is concentrated on some nanostructures, ferroelectric crystals, materials and composites and other materials with specific properties. In this book are presented nanotechnology approaches, modern piezoelectric techniques, physical and mechanical studies of the structure-sensitive properties of the materials. A wide spectrum of mathematical and numerical methods is applied to the solution of different technological, mechanical and physical problems for applications. Great attention is devoted to novel devices with high accuracy, longevity and extended possibilities to work in a large scale of  temperatures and pressure r...

Material Hardship and Internal Locus of Control Over the Prevention of Child Obesity in Low-Income Hispanic Pregnant Women.

Science.gov (United States)

Gross, Rachel S; Mendelsohn, Alan L; Gross, Michelle B; Scheinmann, Roberta; Messito, Mary Jo

2016-07-01

To determine the relations between household material hardships and having a low internal locus of control over the prevention of child obesity in low-income Hispanic pregnant women. We performed a cross-sectional analysis of baseline data collected during a third trimester prenatal visit from women participating in the Starting Early Study, a randomized controlled trial to test the efficacy of a primary care-based family-centered early child obesity prevention intervention. Using multiple logistic regression analyses, we determined whether 4 domains of material hardship (food insecurity, difficulty paying bills, housing disrepair, neighborhood stress), considered individually and also cumulatively, were associated with having a low internal locus of control over the prevention of child obesity. The sample included 559 low-income Hispanic pregnant women, with 60% having experienced at least 1 hardship. Food insecurity was independently associated with a low internal locus of control over the prevention of child obesity (adjusted odds ratio, 2.38; 95% confidence interval, 1.50-3.77), controlling for other hardships and confounders. Experiencing a greater number of material hardships was associated in a dose-dependent relationship with an increased odds of having a low internal locus of control. Prenatal material hardships, in particular food insecurity, were associated with having a lower prenatal internal locus of control over the prevention of child obesity. Longitudinal follow-up of this cohort is needed to determine how relations between material hardships and having a low internal locus of control will ultimately affect infant feeding practices and child weight trajectories. Copyright © 2016 Academic Pediatric Association. Published by Elsevier Inc. All rights reserved.

Introduction to the IEEE International Symposium on Applications of Ferroelectrics and International Symposium on Piezoresponse Force Microscopy and Nanoscale Phenomena in Polar Materials.

Science.gov (United States)

Ye, Zuo-Guang; Tan, Xiaoli; Bokov, Alexei A

2012-09-01

The 20th IEEE International Symposium on Applications of Ferroelectrics (ISAF) was held on July 24-27, 2011, in Vancouver, British Columbia, Canada, jointly with the International Symposium on Piezoresponse Force Microscopy and Nanoscale Phenomena in Polar Materials (PFM). Over a period of four days, approximately 400 scientists, engineers, and students from around the world presented their work and discussed the latest developments in the field of ferroelectrics, related materials, and their applications. It is particularly encouraging to see that a large number of students (115) were attracted to the joint conference and presented high-quality research works. This trend is not only important to this conference series, but more importantly, it is vital to the future of the ferroelectrics field.

Update on Monitoring Technologies for International Safeguards and Fissile Material Verification

International Nuclear Information System (INIS)

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

1999-01-01

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

IAEA support of international research and development of materials for sustainable energy applications

International Nuclear Information System (INIS)

Zeman, Andrej; Kaiser, Ralf; Simon, Aliz

2013-01-01

Full-text:The key mandate of the International Atomic Energy Agency (IAEA) is to promote the peaceful application of nuclear science and technology, verification as well as nuclear safety in the world. This includes a number of activities which aim to support the Member States and stimulate international cooperation in order for sustainable development. During the last 35 years, a well-established mechanism called the Coordinated Research Projects (CRP) has been effectively used to stimulate international research and scientific interaction among the Member States, covering various topics in the nuclear science and technology. Besides direct support of, so called coordinated research, the IAEA is also involved in organizing a number of highly specific international conferences and technical meetings which help to provide a broader platform for the specialist and experts in dedicated areas of nuclear science and technology. In view of support for renewable energy and its application, the IAEA organized series of meetings in 2009 (IEA France), 2010 (UQTR Canada) and 2011 (ANL USA) in order to discuss the scientific and technical issues of particular of national research initiatives related to the hydrogen storage and conversion technologies. All selected outputs of the meetings were published in a technical document publication series which are available to all member states. More recent initiatives are focus on the key nuclear techniques which are extremely valuable in research and development of new innovative materials, methods and technologies, characterization and performance testing of functional materials for innovative energy technologies and their application in sustainable energy sources (nuclear and non-nuclear). It is also important to underline that these programmatic activities are an integral part of the IAEA program on the Road to Rio+20: Applying Nuclear Technology for Sustainable Development. The paper summarizes the IAEA actions relevant to the

How to improve the irradiation conditions for the International Fusion Materials Irradiation Facility

CERN Document Server

Daum, E

2000-01-01

The accelerator-based intense D-Li neutron source International Fusion Materials Irradiation Facility (IFMIF) provides very suitable irradiation conditions for fusion materials development with the attractive option of accelerated irradiations. Investigations show that a neutron moderator made of tungsten and placed in the IFMIF test cell can further improve the irradiation conditions. The moderator softens the IFMIF neutron spectrum by enhancing the fraction of low energy neutrons. For displacement damage, the ratio of point defects to cascades is more DEMO relevant and for tritium production in Li-based breeding ceramic materials it leads to a preferred production via the sup 6 Li(n,t) sup 4 He channel as it occurs in a DEMO breeding blanket.

IFMIF (International Fusion Materials Irradiation Facility) key element technology phase interim report

Energy Technology Data Exchange (ETDEWEB)

Nakamura, Hiroo; Ida, Mizuho; Sugimoto, Masayoshi; Takeuchi, Hiroshi; Yutani, Toshiaki (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2002-03-01

Activities of International Fusion Materials Irradiation Facility (IFMIF) have been performed under an IEA collaboration since 1995. IFMIF is an accelerator-based deuteron (D{sup +})-lithium (Li) neutron source designed to produce an intense neutron field (2 MW/m{sup 2}, 20 dpa/year for Fe) in a volume of 500 cm{sup 3} for testing candidate fusion materials. In 2000, a 3 year Key Element technology Phase (KEP) of IFMIF was started to reduce the key technology risk factors. This interim report summarizes the KEP activities until mid 2001 in the major project work-breakdown areas of accelerator, target, test facilities and design integration. (author)

PATRAM '92: 10th international symposium on the packaging and transportation of radioactive materials

International Nuclear Information System (INIS)

1992-01-01

This document provides the papers presented by Sandia Laboratories at PATRAM '92, the tenth International symposium on the Packaging and Transportation of Radioactive Materials held September 13--18, 1992 in Yokohama City, Japan. Individual papers have been cataloged separately

Hazard evaluation of The International Fusion Materials Irradiation Facility

Energy Technology Data Exchange (ETDEWEB)

Burgazzi, Luciano [ENEA-Centro Ricerche ' Ezio Clementel' , Advanced Physics Technology Division, Via Martiri di Monte Sole, 4, 40129 Bologna (Italy)]. E-mail: burgazzi@bologna.enea.it

2005-01-15

The International Fusion Materials Irradiation Facility (IFMIF) is aimed to provide an intense neutron source by a high current deuteron linear accelerator and a high-speed lithium flow target, for testing candidate materials for fusion. Liquid lithium is being circulated through a loop and is kept at a temperature above its freezing point. In the frame of the design phase called Key Element technology Phase (KEP), jointly performed by an international team to verify the most important risk factors, safety assessment of the whole plant has been required in order to identify the hazards associated with the plant operation. This paper discusses the safety assessments that were performed and their outcome: Failure Mode and Effect Analysis (FMEA) approach has been adopted in order to accomplish the task. Main conclusions of the study is that, on account of the safety and preventive measures adopted, potential plant related hazards are confined within the IFMIF security boundaries and great care must be exercised to protect workers and site personnel from operating the plant. The analysis has provided as a result a set of Postulated Initiating Events (PIEs), that is off-normal events, that could result in hazardous consequences for the plant, together with the total frequency and the list of component failures which could induce the PIE: this assures the exhaustive list of major initiating events of accident sequences, helpful to the further accident sequence analysis phase. Finally, for each one of the individuated PIEs, the evaluation of the accident evolution, in terms of effects on the plant and relative countermeasures, has allowed to verify that adequate measures are being taken both to prevent the accident occurrence and to cope with the accident consequences, thus assuring the fulfilment of the safety requirements.

International conference on security of nuclear material and radioactive sources opens in Stockholm

International Nuclear Information System (INIS)

2001-01-01

The IAEA develops basic guidelines that have proven to be of significant importance in the development of national physical protection systems and international agreements. The IAEA has initiated a number of activities, including training, technology transfer and peer review, to support Member States in improving their nuclear material accountancy and physical protection systems at State and facility levels. The Agency also maintains a database of reported incidents. The Conference is organized by the IAEA, hosted by Swedish Nuclear Power Inspectorate and held in co-operation with the World Customs Organization, the International Criminal Police Organization (INTERPOL) and the European Police Office

PREFACE: 2nd International Conference on Innovative Materials, Structures and Technologies

Science.gov (United States)

Ručevskis, Sandris

2015-11-01

The 2nd International Conference on Innovative Materials, Structures and Technologies (IMST 2015) took place in Riga, Latvia from 30th September - 2nd October, 2015. The first event of the conference series, dedicated to the 150th anniversary of the Faculty of Civil Engineering of Riga Technical University, was held in 2013. Following the established tradition, the aim of the conference was to promote and discuss the latest results of industrial and academic research carried out in the following engineering fields: analysis and design of advanced structures and buildings; innovative, ecological and energy efficient building materials; maintenance, inspection and monitoring methods; construction technologies; structural management; sustainable and safe transport infrastructure; and geomatics and geotechnics. The conference provided an excellent opportunity for leading researchers, representatives of the industrial community, engineers, managers and students to share the latest achievements, discuss recent advances and highlight the current challenges. IMST 2015 attracted over 120 scientists from 24 countries. After rigorous reviewing, over 80 technical papers were accepted for publication in the conference proceedings. On behalf of the organizing committee I would like to thank all the speakers, authors, session chairs and reviewers for their efficient and timely effort. The 2nd International Conference on Innovative Materials, Structures and Technologies was organized by the Faculty of Civil Engineering of Riga Technical University with the support of the Latvia State Research Programme under the grant agreement "INNOVATIVE MATERIALS AND SMART TECHNOLOGIES FOR ENVIRONMENTAL SAFETY, IMATEH". I would like to express sincere gratitude to Juris Smirnovs, Dean of the Faculty of Civil Engineering, and Andris Chate, manager of the Latvia State Research Programme. Finally, I would like to thank all those who helped to make this event happen. Special thanks go to Diana

PREFACE: 17th International Conference on Textures of Materials (ICOTOM 17)

Science.gov (United States)

Skrotzki, Werner; Oertel, Carl-Georg

2015-04-01

The 17th International Conference on Textures of Materials (ICOTOM 17) took place in Dresden, Germany, August 24-29, 2014. It belongs to the "triennial" series of ICOTOM meetings with a long tradition, starting in 1969 - Clausthal, 1971 - Cracow, 1973 - Pont-à-Mousson, 1975 - Cambridge, 1978 - Aachen, 1981 - Tokyo, 1984 - Noordwijkerhout, 1987 - Santa Fe, 1990 - Avignon, 1993 - Clausthal, 1996 - Xian, 1999 - Montreal, 2002 - Seoul, 2005 - Leuven, 2008 - Pittsburgh, 2011 - Mumbai, 2014 - Dresden. ICOTOM 17 was hosted by the Dresden University of Technology, Institute of Structural Physics. Following the tradition of the ICOTOM conferences, the main focus of ICOTOM-17 was to promote and strengthen the fundamental understanding of the basic processes that govern the formation of texture and its relation to the properties of polycrystalline materials. Nonetheless, it was the aim to forge links between basic research on model materials and applied research on engineering materials of technical importance. Thus, ICOTOM 17 provided a forum for the presentation and discussion of recent progress in research of texture and related anisotropy of mechanical and functional properties of all kinds of polycrystalline materials including natural materials like rocks. Particular attention was paid to recent advances in texture measurement and analysis as well as modeling of texture development for all kinds of processes like solidification, plastic deformation, recrystallization and grain growth, phase transformations, thin film deposition, etc. Hence, ICOTOM 17 was of great interest to materials scientists, engineers from many different areas and geoscientists. The topics covered by ICOTOM 17 were: 1. Mathematical, numerical and statistical methods of texture analysis 2. Deformation textures 3. Crystallization, recrystallization and growth textures 4. Transformation textures 5. Textures in functional materials 6. Textures in advanced materials 7. Textures in rocks 8. Texture

Communications issues for international radioactive materials transport, Post 9/11

Energy Technology Data Exchange (ETDEWEB)

Brown, A.A. [International Transport, BNFL, Warrington, Cheshire (United Kingdom); Hartenstein, M. [Transport External Affairs, Marketing, Sales and Projects Div., Cogema Logistics, Saint Quentin en Yvelines (France); Nawano, M. [Transport Headquarters, Overseas Reprocessing Committee, Tokyo (Japan)

2004-07-01

The terrorist attacks of September 11{sup th} 2001 in New York and Washington (9/11) have increased government, public and media concern over terrorist attacks in general and attack on transport systems in particular. Antinuclear groups have increasingly made unsubstantiated claims about the terrorist threat to Radioactive Materials Transport and the consequences of such a threat being realised. At the same time, the international and national security regulations relating to Nuclear Materials Transport have been reviewed and tightened since 9/11. These changes have in some cases restricted the information that can be made publicly available. It is against this background that the Industry must operate and seek to inform the public through its communications activities whilst remaining within the new security framework of security regulations. These activities must necessarily provide sufficient information to counter the incorrect claims made by opponents, allay fears of the public as far as possible and provide factual and scientifically rigorous data without compromising security.

Communications issues for international radioactive materials transport, Post 9/11

International Nuclear Information System (INIS)

Brown, A.A.; Hartenstein, M.; Nawano, M.

2004-01-01

The terrorist attacks of September 11 th 2001 in New York and Washington (9/11) have increased government, public and media concern over terrorist attacks in general and attack on transport systems in particular. Antinuclear groups have increasingly made unsubstantiated claims about the terrorist threat to Radioactive Materials Transport and the consequences of such a threat being realised. At the same time, the international and national security regulations relating to Nuclear Materials Transport have been reviewed and tightened since 9/11. These changes have in some cases restricted the information that can be made publicly available. It is against this background that the Industry must operate and seek to inform the public through its communications activities whilst remaining within the new security framework of security regulations. These activities must necessarily provide sufficient information to counter the incorrect claims made by opponents, allay fears of the public as far as possible and provide factual and scientifically rigorous data without compromising security

5. International conference on materials science and condensed matter physics and symposium 'Electrical methods of materials treatment'. Abstracts

International Nuclear Information System (INIS)

2010-09-01

This book includes abstracts of the communications presented at the 5th International Conference on Materials Science and Condensed-Matter Physics and at the Symposium dedicated to the 100th anniversary of academician Boris Lazarenko, the prominent scientist and inventor, the first director of the Institute of Applied Physics of the Academy of Sciences of Moldova. The abstracts presented in the book cover a vast range of subjects, such as: advanced materials and fabrication processes; methods of crystal growth, post-growth technological processes, doping and implantation, fabrication of solid state structures; defect engineering, engineering of molecular assembly; methods of nanostructures and nano materials fabrication and characterization; quantum wells and superlattices; nano composite, nanowires and nano dots; fullerenes and nano tubes, molecular materials, meso- and nano electronics; methods of material and structure characterization; structure and mechanical characterization; optical, electrical, magnetic and superconductor properties, transport processes, nonlinear phenomena, size and interface effects; advances in condensed matter theory; theory of low dimensional systems; modelling of materials and structure properties; development of theoretical methods of solid-state characterization; phase transition; advanced quantum physics for nano systems; device modelling and simulation, device structures and elements; micro- and optoelectronics; photonics; microsensors and micro electro-mechanical systems; microsystems; degradation and reliability, solid-state device design; theory and advanced technologies of electro-physico-chemical and combined methods of materials machining and treatment, including modification of surfaces; theory and advanced technologies of using electric fields, currents and discharges so as to intensify heat mass-transfer, to raise the efficiency of treatment of materials, of biological preparations and foodstuff; modern equipment for

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

International Nuclear Information System (INIS)

1981-10-01

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

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

Energy Technology Data Exchange (ETDEWEB)

1981-10-01

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

Electrochemical Disinfection Feasibility Assessment Materials Evaluation for the International Space Station

Science.gov (United States)

Rodriquez, Branelle; Shindo, David; Montgomery, Eliza

2013-01-01

The International Space Station (ISS) Program recognizes the risk of microbial contamination in their potable and non-potable water sources. The end of the Space Shuttle Program limited the ability to send up shock kits of biocides in the event of an outbreak. Currently, the United States Orbital Segment water system relies primarily on iodine to mitigate contamination concerns, which has been successful in remediating the small cases of contamination documented. However, a secondary method of disinfection is a necessary investment for future space flight. Over the past year, NASA Johnson Space Center has investigated the development of electrochemically generated systems for use on the ISS. These systems include: hydrogen peroxide, ozone, sodium hypochlorite, and peracetic acid. To use these biocides on deployed water systems, NASA must understand of the effect these biocides have on current ISS materials prior to proceeding forward with possible on-orbit applications. This paper will discuss the material testing that was conducted to assess the effects of the biocides on current ISS materials.

Materiality in Public Sector Financial Audit: International Practice and the Opinion of Brazilian Experts

OpenAIRE

Juliane Madeira Leitão; José Alves Dantas

2016-01-01

Materiality in private sector financial audit is a topic that has been relatively well developed in the literature. Specific research in this regard in public sector auditing, on the other hand, is scarce at the international level and absent in Brazil. In view of this, the purpose of this study was to identify the parameters used to determine materiality in public sector financial audit. To this end, we sent questionnaires to the 192 Supreme Audit Institutions that are members of INTOSAI and...

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

International Nuclear Information System (INIS)

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

1979-11-01

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

Proceedings of the 4th international symposium on material testing reactors

International Nuclear Information System (INIS)

Ishihara, Masahiro; Suzuki, Masahide

2012-03-01

This report is the Proceedings of the fourth International Symposium on Material Testing Reactors hosted by Japan Atomic Energy Agency (JAEA). The first symposium was held on 2008, at the Oarai Research and Development Center of JAEA, the second, 2009, Idaho National Laboratory (INL) of United States and the third 2010, Nuclear Research Institute (NRI) in Czech Republic to exchange information for deep mutual understanding of material testing reactors. The fourth symposium was originally scheduled to be held INVAP in Argentina. However, the aftermath of volcanic explosion at Chili forced the symposium to change place. Total 111 participants attended from Argentina, Belgium, France, Germany, Indonesia, Malasia, Korea, South Africa, Switzerland, the United State and Japan. This symposium addressed the general topics of 'status and future plan of material testing reactors', 'advancement of irradiation technology', 'expansion of industry use(RI)', 'facility, upgrade, aging management', 'new generation MTR', 'advancement of PIE technology', 'development of advanced driver fuel', and 'nuclear human resource development(HRD) for next generation', and 39 presentations were made. Furthermore, three topics, 'Necessity of cooperation for Mo-99 production by (n,gamma) reaction', 'Necessity of standardization of irradiation technology' and 'Conceptual design of next generation materials testing reactor by collaboration', were selected and discussed. (author)

Proceedings of the 4th international symposium on material testing reactors

Energy Technology Data Exchange (ETDEWEB)

Ishihara, Masahiro; Suzuki, Masahide [Japan Atomic Energy Agency, Oarai Research and Development Center, Oarai, Ibaraki (Japan)

2012-03-15

This report is the Proceedings of the fourth International Symposium on Material Testing Reactors hosted by Japan Atomic Energy Agency (JAEA). The first symposium was held on 2008, at the Oarai Research and Development Center of JAEA, the second, 2009, Idaho National Laboratory (INL) of United States and the third 2010, Nuclear Research Institute (NRI) in Czech Republic to exchange information for deep mutual understanding of material testing reactors. The fourth symposium was originally scheduled to be held INVAP in Argentina. However, the aftermath of volcanic explosion at Chili forced the symposium to change place. Total 111 participants attended from Argentina, Belgium, France, Germany, Indonesia, Malasia, Korea, South Africa, Switzerland, the United State and Japan. This symposium addressed the general topics of 'status and future plan of material testing reactors', 'advancement of irradiation technology', 'expansion of industry use(RI)', 'facility, upgrade, aging management', 'new generation MTR', 'advancement of PIE technology', 'development of advanced driver fuel', and 'nuclear human resource development(HRD) for next generation', and 39 presentations were made. Furthermore, three topics, 'Necessity of cooperation for Mo-99 production by (n,gamma) reaction', 'Necessity of standardization of irradiation technology' and 'Conceptual design of next generation materials testing reactor by collaboration', were selected and discussed. (author)

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

International Nuclear Information System (INIS)

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

1979-01-01

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

7. International conference on materials science and condensed matter physics. Abstracts

International Nuclear Information System (INIS)

2014-09-01

This book includes the abstracts of the communications presented at the 7th International Conference on Materials Science and Condensed Matter Physics, traditional biennial meeting organized by the Institute of Applied Physics of the Academy of Sciences of Moldova (IAP) which celebrates this year its 50th anniversary. The conference reports have been delivered in a broad range of topics in materials science, condensed matter physics, electrochemistry reflecting the research results of the scientific staff and Ph.D. students from the IAP as well as those by distinguished guests from different countries. The abstracts cover special issues of modern theoretical and experimental physics and advanced technology, such as advances in condensed matter theory; theory of low dimensional systems; modelling of materials and structural properties; ordering and phase transitions; quantum optics and electronics; strong correlated electronic systems; crystal growth; electronic processes and transport properties of semiconductors and superconductors; ordering processes in magnetic and multiferroic systems; interaction of light and matter, and optical phenomena; properties of composites, meta materials and molecular materials; crystal engineering of solid state structures; metal-organic materials; porous materials; advanced materials with magnetic, luminescent, nonlinear optical , thermoelectric, catalytic, analytic and pharmaceutical properties; defects engineering and mechanical properties; crystallography of organic, inorganic and supramolecular compounds; advanced physics of nanosystems; methods of nanostructures and nanomaterials fabrication and characterization; electronic properties of quantum wells, superlattices, nanowires and nanodots; meso- and nanoelectronics, optical processes in nanostructures; emerging phenomena in nanocomposites and nanomaterials; device modelling and simulation, device structures and elements; photovoltaics: crystals, thin films, nanoparticles

Nuclear data needs for neutron spectrum tailoring at International Fusion Materials Irradiation Facility (IFMIF)

International Nuclear Information System (INIS)

Sugimoto, Masayoshi

2001-01-01

International Fusion Materials Irradiation Facility (IFMIF) is a proposal of D-Li intense neutron source to cover all aspects of the fusion materials development in the framework of IEA collaboration. The new activity has been started to qualifying the important technical issues called Key Element technology Phase since 2000. Although the neutron spectrum can be adjusted by changing the incident beam energy, it is favorable to be carried out many irradiation tasks at the same time under the unique beam condition. For designing the tailored neutron spectrum, neutron nuclear data for the moderator-reflector materials up to 50 MeV are required. The data for estimating the induced radioactivity is also required to keep the radiation level low enough at maintenance time. The candidate materials and the required accuracy of nuclear data are summarized. (author)

Nuclear data needs for neutron spectrum tailoring at International Fusion Materials Irradiation Facility (IFMIF)

Energy Technology Data Exchange (ETDEWEB)

Sugimoto, Masayoshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2001-03-01

International Fusion Materials Irradiation Facility (IFMIF) is a proposal of D-Li intense neutron source to cover all aspects of the fusion materials development in the framework of IEA collaboration. The new activity has been started to qualifying the important technical issues called Key Element technology Phase since 2000. Although the neutron spectrum can be adjusted by changing the incident beam energy, it is favorable to be carried out many irradiation tasks at the same time under the unique beam condition. For designing the tailored neutron spectrum, neutron nuclear data for the moderator-reflector materials up to 50 MeV are required. The data for estimating the induced radioactivity is also required to keep the radiation level low enough at maintenance time. The candidate materials and the required accuracy of nuclear data are summarized. (author)

International Conference on Materials Science and Technology (ICMST 2012)

Science.gov (United States)

Joseph, Ginson P.

2015-02-01

FROM THE CONVENOR'S DESK The Department of Physics, St. Thomas College Pala, is highly privileged to organize an International Conference on Materials Science and Technology (ICMST 2012) during 10-14 June 2012, and as Convenor of the conference it is with legitimate pride and immense gratitude to God that I remember the most enthusiastic responses received for this from scientists all over the world. In a time of tremendous revolutionary changes in Materials Science and Technology, it is quite in keeping with the tradition of a pioneering institute that St. Thomas College is, to have risen to the occasion to make this conference a reality. We have no doubt that this proved to be a historic event, a real breakthrough, not only for us the organizers but also for all the participants. A conference of this kind provides a nonpareil, a distinctly outstanding platform for the scholars, researchers and the scientists to discuss and share ideas with delegates from all over the world. This had been most fruitful to the participants in identifying new collaborations and strengthening existing relations. That experts of diverse disciplines from across the world were sitting under one roof for five days, exchanging views and sharing findings, was a speciality of this conference. The event has evoked excellent responses from all segments of the Materials Science community worldwide. 600 renowned scholars from 28 countries participated in this. We were uniquely honoured to have Prof. C.N.R. Rao, Chairman, Scientific Advisory Council to the Prime Minister of India, to inaugurate this conference. May I take this opportunity to thank all those who have contributed their valuable share, diverse in tone and nature, in the making of this conference. My whole hearted gratitude is due to the international and national members of the advisory committee for their valuable guidance and involvement. I place on record my heartfelt gratitude to our sponsors. I am sure that this conference has

Radioactive materials and nuclear fuel transport requirements in Poland in the light of international regulations

International Nuclear Information System (INIS)

Musialowicz, T.

1977-01-01

National regulations for the transport of radioactive materials and nuclear fuel in Poland are discussed. Basic transport requirements and regulations, transport experience including transport accidents and emergency service are described. The comparison with international regulations is given

PREFACE: International Conference on Functional Materials and Nanotechnologies (FM&NT2012)

Science.gov (United States)

Sternberg, Andris; Muzikante, Inta; Sarakovskis, Anatolijs; Grinberga, Liga

2012-08-01

The International Conference Functional Materials and Nanotechnologies (FM&NT - 2012) was held in Riga, 17-20 April 2012 at the Institute of Solid State Physics, University of Latvia (ISSP UL). The conference was organised by ISSP UL in co-operation with National Research programme in Materials Science and Information Technologies of Latvia. The purpose of this series of conferences is to bring together scientists, researchers, engineers and students from universities, research institutes and related industrial companies working in the field of advanced material science, energy and materials technologies. The contributions of the participants were grouped according to three main topics of the conference: 1. Multifunctional Materials including advanced inorganic, organic and hybrid materials; ferroics; multiscale and multiphenomenal material modeling and simulation 2. Nanotechnologies including progressive methods, technologies and design for investigation of nanoparticles, nanostructures, nanocomposites, thin films and coatings; 3. Energy including perspective materials and technologies for renewable and hydrogen energy, fuel cells, photovoltaics and developing diverse energy systems. A special section devoted to Organic Materials was organized to commemorate a long-time organizer of the FM&NT conference series, Dr. habil. phys, academician Inta Muzikante who passed away on 15 February 2012. The number of registered participants from 21 countries was nearly 300. During the three days of the conference 2 plenary, 16 invited, 54 oral reports and 184 posters were presented. 64 papers, based on these reports, are included in this volume of IOP Conference Series: Materials Science and Engineering. Additional information about FM&NT-2012 is available at its homepage http://www.fmnt.lu.lv. The Organizing Committee would like to thank all the speakers, contributors, session chairs, referees and other involved staff for their efforts in making the FM&NT-2012 successful. The

Proceedings of the international workshop on structural analyses bridging over between amorphous and crystalline materials (SABAC2008)

International Nuclear Information System (INIS)

Shamoto, Shin-ichi; Kodama, Katsuaki

2008-07-01

International workshop entitled 'Structural Analyses Bridging over between Amorphous and Crystalline Materials' (SABAC2008) was held on January 10 and 11, 2007 at Techno Community Square 'RICOTTI' in Tokai. Amorphous and crystalline materials are studied historically by various approaches. Recent industrial functional materials such as optical memory material, thermoelectric material, hydrogen storage material, and ionic conductor have intrinsic atomic disorders in their lattices. These local lattice disorders cannot be studied by conventional crystal structure analyses such as Rietveld analysis. Similar difficulty also exists in the structure analysis of nanomaterials. In the workshop, new approaches to the structural analysis on these materials were discussed. This report includes abstracts and materials of the presentations in the workshop. (author)

Accelerator conceptual design of the international fusion materials irradiation facility

International Nuclear Information System (INIS)

Sugimoto, M.; Kinsho, M.; Teplyakov, V.; Berwald, D.; Bruhwiler, D.; Peakock, M.; Rathke, J.; Deitinghoff, H.; Klein, H.; Pozimski, Y.; Volk, K.; Miyahara, A.; Olivier, M.; Piechowiak, E.; Tanabe, Y.

1998-01-01

The accelerator system of the international fusion materials irradiation facility (IFMIF) provides the 250-mA, 40-MeV continuous-wave deuteron beam at one of the two lithium target stations. It consists of two identical linear accelerator modules, each of which independently delivers a 125-mA beam to the common footprint of 20 cm x 5 cm at the target surface. The accelerator module consists of an ion injector, a 175 MHz RFQ and eight DTL tanks, and rf power supply system. The requirements for the accelerator system and the design concept are described. The interface issues and operational considerations to attain the proposed availability are also discussed. (orig.)

Influence of abutment materials on the implant-abutment joint stability in internal conical connection type implant systems.

Science.gov (United States)

Jo, Jae-Young; Yang, Dong-Seok; Huh, Jung-Bo; Heo, Jae-Chan; Yun, Mi-Jung; Jeong, Chang-Mo

2014-12-01

This study evaluated the influence of abutment materials on the stability of the implant-abutment joint in internal conical connection type implant systems. Internal conical connection type implants, cement-retained abutments, and tungsten carbide-coated abutment screws were used. The abutments were fabricated with commercially pure grade 3 titanium (group T3), commercially pure grade 4 titanium (group T4), or Ti-6Al-4V (group TA) (n=5, each). In order to assess the amount of settlement after abutment fixation, a 30-Ncm tightening torque was applied, then the change in length before and after tightening the abutment screw was measured, and the preload exerted was recorded. The compressive bending strength was measured under the ISO14801 conditions. In order to determine whether there were significant changes in settlement, preload, and compressive bending strength before and after abutment fixation depending on abutment materials, one-way ANOVA and Tukey's HSD post-hoc test was performed. Group TA exhibited the smallest mean change in the combined length of the implant and abutment before and after fixation, and no difference was observed between groups T3 and T4 (P>.05). Group TA exhibited the highest preload and compressive bending strength values, followed by T4, then T3 (Pabutment material can influence the stability of the interface in internal conical connection type implant systems. The strength of the abutment material was inversely correlated with settlement, and positively correlated with compressive bending strength. Preload was inversely proportional to the frictional coefficient of the abutment material.

11th International Space Conference on Protection of Materials and Structures from Space Environment

CERN Document Server

2017-01-01

The proceedings published in this book document and foster the goals of the 11th International Space Conference on “Protection of Materials and Structures from Space Environment” ICPMSE-11 to facilitate exchanges between members of the various engineering and science disciplines involved in the development of space materials. Contributions cover aspects of interaction with space environment of LEO, GEO, Deep Space, Planetary environments, ground-based qualification and in-flight experiments, as well as lessons learned from operational vehicles that are closely interrelated to disciplines of atmospheric sciences, solar-terrestrial interactions and space life sciences.

Fracture Toughness Round Robin Test International in pressure tube materials

International Nuclear Information System (INIS)

Villagarcia, M.P.; Liendo, M.F.

1993-01-01

Part of the pressure tubes surveillance program of CANDU type reactors is to determine the fracture toughness using a special fracture specimen and test procedure. Atomic Energy of Canada Limited decided to hold a Round Robin Test International and 9 laboratories participated worldwide in which several pressure tube materials were selected: Zircaloy-2, Zr-2.5%Nb cold worked and Zr-2.5%Nb heat treated. The small specimens used held back the thickness and curvature of the tube. J-R curves at room temperature were obtained and the crack extension values were determined by electrical potential drop techniques. These values were compared with results generated from other laboratories and a bid scatter was founded. It could be due to slight variations in the test method or inhomogeneity of the materials and a statistical study must be done to see if there is any pattern. The next step for the Round Robin Test would be to make some modifications in the test method in order to reduce the scatter. (Author)

Development of advanced material composites for use as internal insulation for LH2 tanks (gas layer concept)

Science.gov (United States)

Gille, J. P.

1972-01-01

A program is described that was conducted to develop an internal insulation system for potential application to the liquid hydrogen tanks of a reusable booster, where the tanks would be subjected to repeated high temperatures. The design of the internal insulation is based on a unique gas layer concept, in which capillary or surface tension effects are used to maintain a stable gas layer, within a cellular core structure, between the tank wall and the contained liquid hydrogen. Specific objectives were to select materials for insulation systems that would be compatible with wall temperatures of 350 F and 650 F during reentry into the earth's atmosphere, and to fabricate and test insulation systems under conditions simulating the operating environment. A materials test program was conducted to evaluate the properties of candidate materials at elevated temperatures and at the temperature of liquid hydrogen, and to determine the compatibility of the materials with a hydrogen atmosphere at the appropriate elevated temperature. The materials that were finally selected included Kapton polyimide films, silicone adhesives, fiber glass batting, and in the case of the 350 F system, Teflon film.

International Fusion Materials Irradiation Facility conceptual design activity. Present status and perspective

International Nuclear Information System (INIS)

Kondo, Tatsuo; Noda, Kenji; Oyama, Yukio

1998-01-01

For developing the materials for nuclear fusion reactors, it is indispensable to study on the neutron irradiation behavior under fusion reactor conditions, but there is not any high energy neutron irradiation facility that can simulate fusion reactor conditions at present. Therefore, the investigation of the IFMIF was begun jointly by Japan, USA, Europe and Russia following the initiative of IEA. The conceptual design activities were completed in 1997. As to the background and the course, the present status of the research on heavy irradiation and the testing means for fusion materials, the requirement and the technical basis of high energy neutron irradiation, and the international joint design activities are reported. The materials for fusion reactors are exposed to the neutron irradiation with the energy spectra up to 14 MeV. The requirements from the users that the IFMIF should satisfy, the demand of the tests for the materials of prototype and demonstration fusion reactors and the evaluation of the neutron field characteristics of the IFMIF are discussed. As to the conceptual design of the IFMIF, the whole constitution, the operational mode, accelerator system and target system are described. (K.I.)

PREFACE: 12th International Symposium on Multiscale, Multifunctional and Functionally Graded Materials (FGM 2012)

Science.gov (United States)

Zhou, Zhangjian; Li, Jingfeng; Zhang, Lianmeng; Ge, Changchun

2013-03-01

The 12th International Symposium on Multiscale, Multifunctional and Functionally Graded Materials (FGM-2012) was held in Beijing, China, from 22-36 October 2012. This was part of a series of conferences organized every two years endorsed by International Advisory Committee for FGM's, which serves as a forum for scientists, educators, engineers and young students interested in the development of functionally graded materials (FGM). The series continues from the previous international symposium on FGM held in Sendai, Japan (1990), San Francisco, USA (1992), Lausanne, Switzerland (1994), Tsukuba, Japan (1996), Dresden, Germany (1998), Estes Park, USA (2000), Beijing, China (2002), Leuven, Belgium (2004), Hawaii, USA (2006), Sendai, Japan (2008) and Guimaraes, Portugal (2010). Functionally graded materials are non-uniform materials which are designed with embodied continuous spatial variations in composition and microstructure for the specific purpose of adjusting their thermal, structural, mechanical, biological or functional response to specific application conditions. Such multi-phase materials cover a range of space and time scales, and are best understood by means of a comprehensive multiscale, multiphysics approach. These kinds of materials are presently in the forefront of materials research, receiving worldwide attention. They have a broad range of applications including for example, biomedical, biomechanical, automotive, aerospace, mechanical, civil, nuclear, and naval engineering. New applications are continuously being discovered and developed. The objective of the FGM-2012 intends to provide opportunities for exchanging ideas and discussing state-of-the-art theories, techniques and applications in the fields of multiscale, multifunctional and FGM, through invited lectures, oral and poster presentations. FGM-2012 was organized and hosted by University of Science and Technology Beijing, China, together with Tsing-hua University and Wuhan University of

Uncertainty evaluation in normalization of isotope delta measurement results against international reference materials.

Science.gov (United States)

Meija, Juris; Chartrand, Michelle M G

2018-01-01

Isotope delta measurements are normalized against international reference standards. Although multi-point normalization is becoming a standard practice, the existing uncertainty evaluation practices are either undocumented or are incomplete. For multi-point normalization, we present errors-in-variables regression models for explicit accounting of the measurement uncertainty of the international standards along with the uncertainty that is attributed to their assigned values. This manuscript presents framework to account for the uncertainty that arises due to a small number of replicate measurements and discusses multi-laboratory data reduction while accounting for inevitable correlations between the laboratories due to the use of identical reference materials for calibration. Both frequentist and Bayesian methods of uncertainty analysis are discussed.

International laser safety standardization. From the European perspective with an emphasis on materials processing

Energy Technology Data Exchange (ETDEWEB)

Schulmeister, K [Div. of Life Sciences, Dept. of Radiation Protection, Oesterreichisches Forschungszentrum Seibersdorf, 2444 Seibersdorf (Austria)

1997-08-01

This report reviews international standards relevant to the safety of laser products and laser installations, with an emphasis on the safety of laser materials processing from the European perspective. In the first paragraphs an overview of the international standards organisations, their relative roles and ways of developing new standards is given. In the second part of the report, work currently underway in the respective standards committees is summarised and specific standards dealing with different aspects of laser safety are discussed. An appendix contains a list of standards organised in standards organisations (IEC, ISO and EN). (author)

International laser safety standardization. From the European perspective with an emphasis on materials processing

International Nuclear Information System (INIS)

Schulmeister, K.

1997-08-01

This report reviews international standards relevant to the safety of laser products and laser installations, with an emphasis on the safety of laser materials processing from the European perspective. In the first paragraphs an overview of the international standards organisations, their relative roles and ways of developing new standards is given. In the second part of the report, work currently underway in the respective standards committees is summarised and specific standards dealing with different aspects of laser safety are discussed. An appendix contains a list of standards organised in standards organisations IEC, ISO and EN). (author)

Radiation protection - Monitoring of workers occupationally exposed to a risk of internal contamination with radioactive material

International Nuclear Information System (INIS)

2006-01-01

In the course of employment, individuals might work with radioactive materials that, under certain circumstances, could be taken into the body. Protecting workers against risks of incorporated radionuclides requires the monitoring of potential intakes and/or the quantification of actual intakes and exposures. The selection of measures and programmes for this purpose requires decisions concerning methods, techniques, frequencies etc. for measurements and dose assessment. The criteria permitting the evaluation of the necessity of such a monitoring programme or for the selection of methods and frequencies of monitoring usually depend upon the legislation, the purpose of the radiation protection programme, the probabilities of potential radionuclide intakes, and the characteristics of the materials handled. This International Standard offers guidance for the decision whether a monitoring programme is required and how it should be designed. Its intention is to optimise the efforts for such a monitoring programme consistent with legal requirements and with the purpose of the radiation protection programme. Recommendations of international expert bodies and international experience with the practical application of these recommendations in radiation protection programmes have been considered in the development of this International Standard. Its application facilitates the exchanges of information between authorities, supervisory institutions and employers. The International Standard is not a substitute for legal requirements. In the International Standard, the word 'shall' is used to denote a requirement and no deviation is allowed. The word 'should' is used to denote a recommendation from which justified deviations are allowed. The word 'may' is used to denote permission

Comparison Of Internal Adaptation Of Fixed Restorations Fabricated From Four Different Materials By A Three Axis Mill

Science.gov (United States)

2016-06-26

COMP ARIS ON OF INTERNAL ADAPTATION OF FIXED RESTO RA TIO NS FABRICATED FROM FOUR DIFFERENT MATERIALS BY A THREE-AXIS MILL by Bryan Paul...MATERIALS BY A THREE-AXIS MILL is appropriately acknowledged and, beyond brief excerpts, is with the permission of the copyright owner. ~r2L~ Bryan Paul...RESTORATIONS FABRICATED FROM FOUR DIFFERENT MATERIALS BY A THREE-AXIS MILL LCDR Bryan Paul Rasmussen, DC USN Prosthodontics Dept., 2016 Directed by

Fissile materials and international security in the post-Cold War world

International Nuclear Information System (INIS)

Anon.

1996-01-01

It is essential that members of industry, government and international organizations be able to come together to discuss the latest developments in this vital field at events such as this. Given the number of years this organization has devoted to the issue, the INMM must find it interesting that the control of fissile materials has become such a high-profile issue in the policy and political communities. But, this evolution in policy is a natural outgrowth of the changing world situation. While just 10 years ago the US and Soviet Union were churning out the fissile materials needed for weapons, today these former rivals are working together, hand in hand, to corral the danger posed by these materials. And, while it is clear that the world no longer lives on the edge of nuclear war, the nuclear danger still exists, though in a less obvious and perhaps more insidious form. It is a great challenge in this post-Cold War world to contain this nuclear threat. It is prudent and necessary for the US to be in the forefront of efforts to address and tame this problem. The fundamental threat posed by the proliferation of nuclear weapons and materials is a direct challenge to US and world security. President Clinton has clearly recognized the changed nature of the nuclear danger. To meet this challenge, he has labored to put in place a comprehensive and integrated plan for addressing this threat. The US Department of Energy has a unique role in this effort because, as an institution with many decades of experience in fissile material matters, it is able to provide expertise and technical analyses that are essential in defining and implementing policy prescriptions. The president's comprehensive plan to prevent nuclear proliferation and reduce the danger posed by weapons-usable nuclear materials has four essential elements: secure existing nuclear material stockpiles; limit fissile material production and use, eliminate warheads, and strengthen the nonproliferation regime

IFMIF-KEP. International fusion materials irradiation facility key element technology phase report

International Nuclear Information System (INIS)

2003-03-01

The International Fusion Materials Irradiation Facility (IFMIF) is an accelerator-based D-Li neutron source designed to produce an intense neutron field that will simulate the neutron environment of a D-T fusion reactor. IFMIF will provide a neutron flux equivalent to 2 MW/m 2 , 20 dpa/y in Fe, in a volume of 500 cm 3 and will be used in the development and qualification of materials for fusion systems. The design activities of IFMIF are performed under an IEA collaboration which began in 1995. In 2000, a three-year Key Element Technology Phase (KEP) of IFMIF was undertaken to reduce the key technology risk factors. This KEP report describes the results of the three-year KEP activities in the major project areas of accelerator, target, test facilities and design integration. (author)

PREFACE: International Symposium on Dynamic Deformation and Fracture of Advanced Materials (D2FAM 2013)

Science.gov (United States)

Silberschmidt, Vadim V.

2013-07-01

Intensification of manufacturing processes and expansion of usability envelopes of modern components and structures in many cases result in dynamic loading regimes that cannot be resented adequately employing quasi-static formulations of respective problems of solid mechanics. Specific features of dynamic deformation, damage and fracture processes are linked to various factors, most important among them being: a transient character of load application; complex scenarios of propagation, attenuation and reflection of stress waves in real materials, components and structures; strain-rate sensitivity of materials properties; various thermo-mechanical regimes. All these factors make both experimental characterisation and theoretical (analytical and numerical) analysis of dynamic deformation and fracture rather challenging; for instance, besides dealing with a spatial realisation of these processes, their evolution with time should be also accounted for. To meet these challenges, an International Symposium on Dynamic Deformation and Fracture of Advanced Materials D2FAM 2013 was held on 9-11 September 2013 in Loughborough, UK. Its aim was to bring together specialists in mechanics of materials, applied mathematics, physics, continuum mechanics, materials science as well as various areas of engineering to discuss advances in experimental and theoretical analysis, and numerical simulations of dynamic mechanical phenomena. Some 50 papers presented at the Symposium by researchers from 12 countries covered various topics including: high-strain-rate loading and deformation; dynamic fracture; impact and blast loading; high-speed penetration; impact fatigue; damping properties of advanced materials; thermomechanics of dynamic loading; stress waves in micro-structured materials; simulation of failure mechanisms and damage accumulation; processes in materials under dynamic loading; a response of components and structures to harsh environment. The materials discussed at D2FAM 2013

The strengthening of international regime of protection of the nuclear materials and other radioactive sources

International Nuclear Information System (INIS)

Shiganbayev, E.

2001-01-01

Full text: The widening of export streams satisfies the interest of any state, but at the same time the interests of individual countries and the whole international community requires the limitation of export of goods and technologies which are potentially dangerous. The decision of this problem, finding of the optimal balance between the devotion of the principles of free trade and the necessity of limiting the danger export is one of the main tasks of the national system of security of the Republic of Kazakhstan. Kazakhstan is a country with a policy of nonproliferation. This important element of the policy of the country, directed to maintenance and strengthening of the international security, becomes the priority trend in the foreign policy of Kazakhstan. The international community decides this problem under the Comprehensive Nuclear Test Ban Treaty (CTBT), Treaty on the Non-Proliferation of Nuclear Weapons (NPT), and the Convention on the Prohibition of the Development Production and Stockpiling of Bacteriological (Biological) and Toxin Weapons and on the Destruction, Convention on the Prohibition of the Development, Production, Stockpiling and Use of Chemical Weapons and Their Destruction. At present there are four international regimes in control with the aim of nonproliferation of the weapons of mass destruction (WMD): The group of the nuclear supplies which deals with the questions of delivery of special nuclear materials and technologies, and also nuclear materials and double function technologies; Australian group works in the sphere of control for materials and technologies of chemical and biological weapons; The regime of the control of rocket technologies functioning with the aim to prevent the proliferation of rockets as means of delivery of weapon of mass destruction; Wassenaar agreement, regime of export control for usual armament, goods and double function technologies. Kazakhstan does not have nuclear weapons and participants in the Agreement

Accelerator conceptual design of the international fusion materials irradiation facility

Energy Technology Data Exchange (ETDEWEB)

Sugimoto, M.; Kinsho, M. [Japan Atomic Energy Res. Inst., Tokai, Ibaraki (Japan). Intense Neutron Source Lab.; Jameson, R.A.; Blind, B. [Los Alamos National Lab., NM (United States); Teplyakov, V. [Institute for High Energy Physics, Moscow (Russian Federation); Berwald, D.; Bruhwiler, D.; Peakock, M.; Rathke, J. [Northrop Grumman Corp., Bethpage, NY (United States); Deitinghoff, H.; Klein, H.; Pozimski, Y.; Volk, K. [Johann Wolfgang Goethe Univ., Frankfurt (Germany). Inst. fur Angewandte Phys.; Ferdinand, R.; Lagniel, J.-M. [CEA Saclay LNS, Gif-sur-Yvette (France); Miyahara, A. [Teikyo Univ., Tokyo (Japan); Olivier, M. [CEA DSM, Saclay, Gif-sur-Yvette (France); Piechowiak, E. [Northrop Grumman Corp., Baltimore, MD (United States); Tanabe, Y. [Toshiba Corp., Tsurumi-ku, Yokohama (Japan)

1998-10-01

The accelerator system of the international fusion materials irradiation facility (IFMIF) provides the 250-mA, 40-MeV continuous-wave deuteron beam at one of the two lithium target stations. It consists of two identical linear accelerator modules, each of which independently delivers a 125-mA beam to the common footprint of 20 cm x 5 cm at the target surface. The accelerator module consists of an ion injector, a 175 MHz RFQ and eight DTL tanks, and rf power supply system. The requirements for the accelerator system and the design concept are described. The interface issues and operational considerations to attain the proposed availability are also discussed. (orig.) 8 refs.

PFMC-16. 16th international conference on plasma-facing materials and components for fusion applications. Abstracts

Energy Technology Data Exchange (ETDEWEB)

NONE

2017-07-01

The performances of fusion devices and of future fusion power plants strongly depend on the plasma-facing materials and components. Resistance to heat and particle loads, compatibility in plasma operations, thermo-mechanical properties, as well as the response to neutron irradiation are critical parameters which need to be understood and tailored from atomistic to component levels. The 16th International Conference on Plasma-Facing Materials and Components for Fusion Applications addresses these issues.

Efficiency Limits of Solar Energy Harvesting via Internal Photoemission in Carbon Materials

Directory of Open Access Journals (Sweden)

Svetlana V. Boriskina

2018-02-01

Full Text Available We describe strategies to estimate the upper limits of the efficiency of photon energy harvesting via hot electron extraction from gapless absorbers. Gapless materials such as noble metals can be used for harvesting the whole solar spectrum, including visible and near-infrared light. The energy of photo-generated non-equilibrium or ‘hot’ charge carriers can be harvested before they thermalize with the crystal lattice via the process of their internal photo-emission (IPE through the rectifying Schottky junction with a semiconductor. However, the low efficiency and the high cost of noble metals necessitates the search for cheaper abundant alternative materials, and we show here that carbon can serve as a promising IPE material candidate. We compare the upper limits of performance of IPE photon energy-harvesting platforms, which incorporate either gold or carbon as the photoactive material where hot electrons are generated. Through a combination of density functional theory, joint electron density of states calculations, and Schottky diode efficiency modeling, we show that the material electron band structure imposes a strict upper limit on the achievable efficiency of the IPE devices. Our calculations reveal that graphite is a good material candidate for the IPE absorber for harvesting visible and near-infrared photons. Graphite electron density of states yields a sizeable population of hot electrons with energies high enough to be collected across the potential barrier. We also discuss the mechanisms that prevent the IPE device efficiency from reaching the upper limits imposed by their material electron band structures. The proposed approach is general and allows for efficient pre-screening of materials for their potential use in IPE energy converters and photodetectors within application-specific spectral windows.

IFMIF-KEP. International fusion materials irradiation facility key element technology phase report

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-03-01

The International Fusion Materials Irradiation Facility (IFMIF) is an accelerator-based D-Li neutron source designed to produce an intense neutron field that will simulate the neutron environment of a D-T fusion reactor. IFMIF will provide a neutron flux equivalent to 2 MW/m{sup 2}, 20 dpa/y in Fe, in a volume of 500 cm{sup 3} and will be used in the development and qualification of materials for fusion systems. The design activities of IFMIF are performed under an IEA collaboration which began in 1995. In 2000, a three-year Key Element Technology Phase (KEP) of IFMIF was undertaken to reduce the key technology risk factors. This KEP report describes the results of the three-year KEP activities in the major project areas of accelerator, target, test facilities and design integration. (author)

Sample environment for neutron scattering measurements of internal stresses in engineering materials in the temperature range of 6 K to 300 K.

Science.gov (United States)

Kirichek, O; Timms, J D; Kelleher, J F; Down, R B E; Offer, C D; Kabra, S; Zhang, S Y

2017-02-01

Internal stresses in materials have a considerable effect on material properties including strength, fracture toughness, and fatigue resistance. The ENGIN-X beamline is an engineering science facility at ISIS optimized for the measurement of strain and stress using the atomic lattice planes as a strain gauge. Nowadays, the rapidly rising interest in the mechanical properties of engineering materials at low temperatures has been stimulated by the dynamic development of the cryogenic industry and the advanced applications of the superconductor technology. Here we present the design and discuss the test results of a new cryogenic sample environment system for neutron scattering measurements of internal stresses in engineering materials under a load of up to 100 kN and in the temperature range of 6 K to 300 K. Complete cooling of the system starting from the room temperature down to the base temperature takes around 90 min. Understanding of internal stresses in engineering materials at cryogenic temperatures is vital for the modelling and designing of cutting-edge superconducting magnets and other superconductor based applications.

International Conference on Microtechnology and Thermal Problems in Electronics (MicroTherm'2015) and International Conference on Smart Engineering of New Materials (SENM'2015)

International Nuclear Information System (INIS)

2016-01-01

The issue covers selected papers presented during the Joint Event of two International Cyclic Conferences: MicroTherm – Microtechnology and Thermal Problems in Electronics and SENM – Smart Engineering of New Materials. The Duoconference was held in Lodz, Poland on 23-25 June 2015. It gathered almost 200 participants from 20 countries. MicroTherm is an International Conference on Microtechnology and Thermal Problems in Electronics that is organised every two years, since 1996. The success of the first seminar devoted to thermal management aspects, and the successive conferences have led us to the eleventh edition. Since the first meeting, the scope of the Conference has expanded, following the progress of electronics. Now, it covers subjects connected with extreme temperature, electronics, sensors and measurement techniques, modelling, simulation, wide band-gap materials, packaging and reliability, renewable energy sources and photonics with special emphasis on microelectronic technologies. The tradition of SENM dates back to 1985 when the First International Conference on Diamond Crystallization under Reduced Pressure was held in Jabłonna, Poland. Since then, the Conference is organised regularly every five years. From the early beginning the main aim of this event was the creation of an international forum of scientists for the presentation of the newest achievements and investigation results in vacuum and plasma techniques, synthesis, characterisation and application of diamond, its derivatives and other wide bandgap materials. Over time, the scope of the conference has expanded to include nanomaterials, biomaterials and new functional materials, in the range of production, design and optimisation of the synthesis and modification technologies. Traditionally, the programme of MicroTherm’2015 and SENM’2015 is comprised of invited talks and regular sessions in the form of planar discussions and poster presentations, which also include a Students’ Session

Material Usage in High Pressure Oxygen Systems for the International Space Station

Science.gov (United States)

Kravchenko, Michael; Sievers, D. Elliott

2014-01-01

The Nitrogen/Oxygen Recharge System (NORS) for the International Space Station (ISS) Program was required as part of the Space Shuttle retirement efforts to sustain the ISS life support systems. The system is designed around a 7000 psia Oxygen or Nitrogen Recharge Tank Assembly which is able to be utilized both internally and externally to the ISS. Material selection and usage were critical to ensure oxygen compatibility for the design, while taking into consideration toxicity, weldability, brazability and general fabrication and assembly techniques. The system uses unique hardware items such a composite overwrap pressure vessel (COPV), high pressure mechanical gauges, compact regulators and valves, quick disconnects, metal tubing and flexhoses. Numerous challenges and anomalies were encountered due to the exotic nature of this project which will be discussed in detail. The knowledge gained from these anomalies and failure resolutions can be applied to more than space applications, but can also be applicable to industry pressurized systems.

International Target Values 2010 for Measurement Uncertainties in Safeguarding Nuclear Materials

Energy Technology Data Exchange (ETDEWEB)

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

2012-12-15

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

2014 International Conference on Manufacturing, Optimization, Industrial and Material Engineering

International Nuclear Information System (INIS)

Gaol, Ford Lumban; Webb, Jeff; Ding, Jun

2014-01-01

The 2nd International Conference on Manufacturing, Optimization, Industrial and Material Engineering 2014 (MOIME 2014), was held at the Grand Mercure Harmoni, Opal Room 3rd Floor, Jakarta, Indonesia, during 29–30 March 2014. The MOIME 2014 conference is designed to bring together researchers, engineers and scientists in the domain of interest from around the world. MOIME 2014 is placed on promoting interaction between the theoretical, experimental, and applied communities, so that a high level exchange is achieved in new and emerging areas within Material Engineering, Industrial Engineering and all areas that relate to Optimization. We would like to express our sincere gratitude to all in the Technical Program Committee who have reviewed the papers and developed a very interesting Conference Program as well as the invited and plenary speakers. This year, we received 97 papers and after rigorous review, 24 papers were accepted. The participants come from 7 countries. There are 4 (four) parallel session and 2 Invited Speakers and one workshop. It is an honour to present this volume of IOP Conference Series: Materials Science and Engineering (MSE) and we deeply thank the authors for their enthusiastic and high-grade contributions. Finally, we would like to thank the conference chairmen, the members of the steering committee, the organizing committee, the organizing secretariat and the financial support from the conference sponsors that allowed the success of MOIME 2014. The Editors of the MOIME 2014 Proceedings Editors Dr Ford Lumban Gaol Jeff Webb, PhD Professor Jun Ding, PhD

International Trade Drives Global Resource Use: A Structural Decomposition Analysis of Raw Material Consumption from 1990-2010.

Science.gov (United States)

Plank, Barbara; Eisenmenger, Nina; Schaffartzik, Anke; Wiedenhofer, Dominik

2018-04-03

Globalization led to an immense increase of international trade and the emergence of complex global value chains. At the same time, global resource use and pressures on the environment are increasing steadily. With these two processes in parallel, the question arises whether trade contributes positively to resource efficiency, or to the contrary is further driving resource use? In this article, the socioeconomic driving forces of increasing global raw material consumption (RMC) are investigated to assess the role of changing trade relations, extended supply chains and increasing consumption. We apply a structural decomposition analysis of changes in RMC from 1990 to 2010, utilizing the Eora multi-regional input-output (MRIO) model. We find that changes in international trade patterns significantly contributed to an increase of global RMC. Wealthy developed countries play a major role in driving global RMC growth through changes in their trade structures, as they shifted production processes increasingly to less material-efficient input suppliers. Even the dramatic increase in material consumption in the emerging economies has not diminished the role of industrialized countries as drivers of global RMC growth.

The Micromorphological Research of the Internal Structure of Chairside CAD/CAM Materials by the Method of Scanning Impulse Acoustic Microscopy (SIAM).

Science.gov (United States)

Goryainova, Kristina E; Morokov, Egor S; Retinskaja, Marina V; Rusanov, Fedor S; Apresyan, Samvel V; Lebedenko, Igor Yu

2018-01-01

The aim of the present work was to compare the elastic properties and internal structure of 4 different CAD/CAM chairside materials, by the method of Scanning Impulse Acoustic Microscopy (SIAM). Four chairside CAD/CAM materials with different structures from hybrid ceramic (VITA Enamic, VITA Zahnfabrik), feldspatic ceramic (VITABlocs Mark II, VITA Zahnfabrik), leucite glass-ceramic (IPS Empress CAD, Ivoclar Vivadent) and PMMA (Telio CAD, Ivoclar Vivadent) were examined by Scanning Impulse Acoustic Microscope (SIAM). The results of micromorphological research of CAD/CAM chairside materials using SIAM method showed differences between the internal structures of these materials. The internal structure of feldspatic and glass-ceramic samples revealed the presence of pores with different sizes, from 10 to 100 microns; the structure of polymer materials rendered some isolated defects, while in the structure of hybrid material, defects were not found. Based on the results obtained from the present study, in cases of chairside production of dental crowns, it would be advisable to give preference to the blocks of hybrid ceramics. Such ceramics devoid of quite large porosity, glazing for CAD/CAM crowns made from leucite glass-ceramic and feldspatic ceramic may be an option. For these purposes, commercially available special muffle furnace for clinical and laboratory individualization and glazing of ceramic prostheses were provided. Further studies are needed to confirm the evidence emerging from the present research.

Communication from the Permanent Mission of the Russian Federation to the International Atomic Energy Agency regarding the export of nuclear material and of certain categories of equipment and other material

International Nuclear Information System (INIS)

2000-01-01

The document reproduces the text of a letter received by the Director general of the IAEA from Permanent Mission of the Russian Federation to the International Atomic Energy Agency concerning the export of nuclear material and of certain categories of equipment and other material

Irradiated stainless steel material constitutive model for use in the performance evaluation of PWR pressure vessel internals

Energy Technology Data Exchange (ETDEWEB)

Rashid, J.Y.; Dunham, R.S. [ANATECH (United States); Demma, A. [Electric Power Research Institute - EPRI (United States)

2011-07-01

Demonstration of component functionality requires analytical simulations of reactor internals behavior. Towards that aim, EPRI has undertaken the development of irradiated material constitutive model and damage criteria for use in global and local finite-element based functionality analysis methodology. The constitutive behavioral regimes of irradiated stainless steel types 316 and 304 materials included in the model consist of: elastic-plastic material response considering irradiation hardening of the stress-strain curve, irradiation creep, stress relaxation, and void swelling. IASCC and degradation of ductility with irradiation are the primary damage mechanisms considered in the model. The material behavior model development consists of two parts: the first part is a user-material subroutine that can interface with a general-purpose finite element computer program to adapt it to the special-purpose of functionality analysis of reactor internals. The second part is a user utility in the form of Excel Spread sheets that permit users to extract a given property, e.g. the elastic-plastic stress-strain curve, creep curve, or void-swelling curve, as function of the relevant independent variables. The development of the model takes full advantage of the significant work that has been undertaken within EPRI's Material Reliability Program (MRP) to improve the knowledge of the material properties of irradiated stainless steels. Data from EPRI's MRP database have been utilized to develop equations that characterize the yield strength, ultimate tensile strength, uniform elongation, total elongation, reduction in area, void swelling and irradiation creep of stainless steels in a PWR environment. It is noted that, while the development of the model's equations has been statistically faithful to the material database, approximations were introduced in the model to ensure appropriate conservatism in the model's application consistently with accepted

Proceedings of the 20th International Conference on Ion Beam Modification of Materials (IBMM 2016)

Science.gov (United States)

Kennedy, John; Elliman, Robert; Mccallum, Jeffrey; Ionescu, Mihail; Markwitz, Andreas

2017-10-01

The papers in this issue of NIMB were presented at the 20th international conference on Ion Beam Modification of Materials (IBMM) held at Te Papa Museum, Wellington, New Zealand from October 30th until November 4th, 2016. This conference continued the proud legacy of New Zealand-born Lord Rutherford and his pioneering research in ion beam physics.

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

International Nuclear Information System (INIS)

2001-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

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

2. International workshop on spallation materials technology

International Nuclear Information System (INIS)

Carsughi, F.; Mansur, L.K.; Sommer, W.F.; Ullmaier, H.

1997-11-01

This document contains 25 papers consisting an abstract prepared by the authors, followed by copies of the presentation viewgraphs used by speakers. The topics were: Target options for SINQ; Overview of the NSNS target system; ISIS target and moderator materials; Trispal project; JHF N-ARENA; Design, load conditions and manufacturing aspect of the ESS MERCURY TARGET unit; Radiation damage simulatiion to measure recoil spectra distribution; Radiation damage calculation to spallation neutron source materials; Hadron-induced neutron production in Pb and U targets from 1-5 GeV; Proton beam effects on W rods, surface cooled by water; Corrosion and fatigue behavior of metals and alloys in high radiation fields; compability of materials with mercury for NSNS target system; Research activities at PSI on structural materials for spallation neutron source; The accelerator production of tritium materials reserach program and Los Alamos National Laboratory; Experimental program on irradiation effects in structural materials of the Trispal project; First pulsed power materials test at Livermore; Plan of thermal shock fracture test at JAERI; Is there a hydrogen problem in target materials in high-power spatllation source?; Materials consideration for the NSNS target; Materials durability issures in spallation neutron source applications; Post-irradiation investigations at the FZJ; Microstructure and hardening of steels containing high helium concentrations; Tensile properties and microstructure of the F82H ferritic-martensitic steel after irradiation in the PIREX facility

PREFACE: International Conference on Advanced Materials (ICAM 2015)

Science.gov (United States)

El-Khateeb, Mohammad Y.

2015-10-01

It is with great pleasure to welcome you to the "International Conference of Advanced Materials ICAM 2015" that will take place at Jordan University of Science and Technology (JUST), Irbid, Jordan. This year, the conference coincides with the coming of spring in Jordan; we hope the participants will enjoy the colors and fragrance of April in Jordan. The call for papers attracted submissions of over a hundred abstracts from twenty one different countries. These papers are going to be classified under four plenary lectures, fifteen invited papers, thirty five oral presentations and more than sixty posters covering the different research areas of the conference. The ICAM conference focuses on new advances in research in the field of materials covering chemical, physical and biological aspects. ICAM includes representatives from academia, industry, governmental and private sectors. The plenary and invited speakers will present, discuss, promote and disseminate research in all fields of advanced materials. Topics range from synthesis, applications, and solid state to nano-materials. In addition, talented junior investigators will present their best ongoing research at a poster session. We have also organized several workshops contiguous to the main conference, such as the one-day workshop on "Particle Surface Modification for Improved Applications". The purpose of this short course was to introduce interested materials technologists to several methodologies that have been developed to modify the surfaces of particulate matter. Moreover, a pre-conference workshop on "Communication in Science" was conducted for young scientists. The main goal of this workshop was to train young scientists in matters of interdisciplinary scientific communications. In addition to the scientific program, the attendees will have a chance to discover the beauty of Jordan, a land of rich history and varied culture. Numerous social events that will provide opportunities to renew old contacts and

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

International Nuclear Information System (INIS)

1986-06-01

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

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

International Nuclear Information System (INIS)

1984-06-01

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

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

Energy Technology Data Exchange (ETDEWEB)

1986-06-01

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

The Micromorphological Research of the Internal Structure of Chairside CAD/CAM Materials by the Method of Scanning Impulse Acoustic Microscopy (SIAM)

Science.gov (United States)

Goryainova, Kristina E.; Morokov, Egor S.; Retinskaja, Marina V.; Rusanov, Fedor S.; Apresyan, Samvel V.; Lebedenko, Igor Yu.

2018-01-01

Aim: The aim of the present work was to compare the elastic properties and internal structure of 4 different CAD/CAM chairside materials, by the method of Scanning Impulse Acoustic Microscopy (SIAM). Methods: Four chairside CAD/CAM materials with different structures from hybrid ceramic (VITA Enamic, VITA Zahnfabrik), feldspatic ceramic (VITABlocs Mark II, VITA Zahnfabrik), leucite glass-ceramic (IPS Empress CAD, Ivoclar Vivadent) and PMMA (Telio CAD, Ivoclar Vivadent) were examined by Scanning Impulse Acoustic Microscope (SIAM). Results: The results of micromorphological research of CAD/CAM chairside materials using SIAM method showed differences between the internal structures of these materials. The internal structure of feldspatic and glass-ceramic samples revealed the presence of pores with different sizes, from 10 to 100 microns; the structure of polymer materials rendered some isolated defects, while in the structure of hybrid material, defects were not found. Conclusion: Based on the results obtained from the present study, in cases of chairside production of dental crowns, it would be advisable to give preference to the blocks of hybrid ceramics. Such ceramics devoid of quite large porosity, glazing for CAD/CAM crowns made from leucite glass-ceramic and feldspatic ceramic may be an option. For these purposes, commercially available special muffle furnace for clinical and laboratory individualization and glazing of ceramic prostheses were provided. Further studies are needed to confirm the evidence emerging from the present research. PMID:29492178

The use of foresight methods in strategic raw materials intelligence - an international review

Science.gov (United States)

Konrat Martins, Marco Antonio; Bodo, Balazs; Falck, Eberhard

2017-04-01

Foresight methods are systematic attempts to look into the longer term future of science, society, economy and technology. There is a range of tools and techniques that can be used individually or combined, most commonly classified into qualitative, quantitative or semi-quantitative methods, that follow an exploratory or normative approach. These tools can help to identify the longer term visions, orienting policy formulation and decisions, triggering actions, among other objectives. There is an identified lack of European strategic foresight knowledge in the raw materials domain. Since the European Raw Materials Initiative was launched in 2008, the EU has been attempting to overcome challenges related to the future access of non-energy and non-agricultural raw materials. In this context, the ongoing H2020 project, MICA (Mineral Intelligence Capacity Analysis, Grant Agreement No. 689648), has been launched to answer to stakeholders needs by consolidating relevant data, determining relevant methods and tools, and investigating Raw Materials Intelligence options for European mineral policy development, all tailored to fit under the umbrella of a European Raw Materials Intelligence Capacity Platform (EU-RMICP). As part of the MICA activities, an assessment of best practices and benchmarks of international raw materials foresight case studies has been carried out in order to review how EU and non-EU countries have employed foresight. A pool of 30 case studies has been collected and reviewed internationally, one third of which were selected for detailed assessment. These were classified according to their background and goals, in function of methods employed, and to the purpose of each method in the study: a total of 12 different methods were identified in these studies. For longer time frames, qualitative predictive methods such as Scenario Development have been repeatedly observed for mineral raw materials foresight studies. Substantial variations were observed in

PATRAM 2004 - The 14th international symposium on the packaging and transportation of radioactive materials. Conference proceedings

International Nuclear Information System (INIS)

2004-01-01

The 14th International Symposium on the Packaging and Transport of Radioactive Materials, PATRAM 2004, was held at the Estrel Convention Center in Berlin, Germany, from 20-24 September 2004. PATRAM '04 was held under the auspices of the German Federal Ministry for Transport, Building and Housing (BMNBW), and was hosted by the German Bundesanstalt fur Materialforschung und -Prufung (BAM). Further, the conference was held in cooperation with the International Atomic Energy Agency (IAEA) and the US Institute for Nuclear Materials Management. As with past PATRAM conferences, this one covered a wide range of topics that are of concern to the nuclear materials transport industry; regulations, operations, technical analyses and testing, design, institutional issues, security, risk assessment and emergency response. Presentation of these topics was provided through a number of fora, plenary presentations, panel presentations, oral presentations, posters and technical tours. Coupled with the opening reception on Monday evening and the coffee breaks, a forum was provided at this PATRAM that allowed all participants ample opportunities to increase their technical knowledge, to learn about compelling issues around the world and to network with colleagues. (orig.)

PATRAM 2004 - The 14th international symposium on the packaging and transportation of radioactive materials. Conference proceedings

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-07-01

The 14th International Symposium on the Packaging and Transport of Radioactive Materials, PATRAM 2004, was held at the Estrel Convention Center in Berlin, Germany, from 20-24 September 2004. PATRAM '04 was held under the auspices of the German Federal Ministry for Transport, Building and Housing (BMNBW), and was hosted by the German Bundesanstalt fur Materialforschung und -Prufung (BAM). Further, the conference was held in cooperation with the International Atomic Energy Agency (IAEA) and the US Institute for Nuclear Materials Management. As with past PATRAM conferences, this one covered a wide range of topics that are of concern to the nuclear materials transport industry; regulations, operations, technical analyses and testing, design, institutional issues, security, risk assessment and emergency response. Presentation of these topics was provided through a number of fora, plenary presentations, panel presentations, oral presentations, posters and technical tours. Coupled with the opening reception on Monday evening and the coffee breaks, a forum was provided at this PATRAM that allowed all participants ample opportunities to increase their technical knowledge, to learn about compelling issues around the world and to network with colleagues. (orig.)

Perspectives on the International and Internal Nuclear Security Regime

International Nuclear Information System (INIS)

Jang, Sung Soon

2015-01-01

The term, 'Nuclear Security' became more familiar to Korean public after the government hosted 2012 Seoul Nuclear Security Summit. Nuclear Security is prevention of, detection of and response to criminal or intentional unauthorized acts involving or directed at nuclear material, other radioactive material, associated facilities, or associated activities. Nuclear Security includes physical protection, security of radioactive sources, nuclear forensics, nuclear smuggling prevention, border monitoring, and cyber security with regard to nuclear and other radiological materials. This abstract will review recent international trends and discuss the nuclear security regime in the Republic of Korea (ROK). The international Nuclear Security Regime has been strengthened. The upcoming Chicago Summit in 2016 and the entry into force of the Amendment of Convention on Physical Protection of Nuclear Materials (CPPNM) will bring major changes in nuclear security. The Republic of Korea hosted the 2012 Seoul Summit and strengthened domestic regime to meet international standards. The ROK has worked hard to contribute to the international security regime and to establish a robust domestic security regime against terrorist threats. Even if the nuclear security regime is robust, Risk-informed Nuclear Security management should be established to meet international standards and to implement effective as well as an efficient nuclear security regime

Perspectives on the International and Internal Nuclear Security Regime

Energy Technology Data Exchange (ETDEWEB)

Jang, Sung Soon [Korea Nuclear Non-proliferation and Control, Daejeon (Korea, Republic of)

2015-10-15

The term, 'Nuclear Security' became more familiar to Korean public after the government hosted 2012 Seoul Nuclear Security Summit. Nuclear Security is prevention of, detection of and response to criminal or intentional unauthorized acts involving or directed at nuclear material, other radioactive material, associated facilities, or associated activities. Nuclear Security includes physical protection, security of radioactive sources, nuclear forensics, nuclear smuggling prevention, border monitoring, and cyber security with regard to nuclear and other radiological materials. This abstract will review recent international trends and discuss the nuclear security regime in the Republic of Korea (ROK). The international Nuclear Security Regime has been strengthened. The upcoming Chicago Summit in 2016 and the entry into force of the Amendment of Convention on Physical Protection of Nuclear Materials (CPPNM) will bring major changes in nuclear security. The Republic of Korea hosted the 2012 Seoul Summit and strengthened domestic regime to meet international standards. The ROK has worked hard to contribute to the international security regime and to establish a robust domestic security regime against terrorist threats. Even if the nuclear security regime is robust, Risk-informed Nuclear Security management should be established to meet international standards and to implement effective as well as an efficient nuclear security regime.

Biobased, Internally pH-Sensitive Materials: Immobilized Yellow Fluorescent Protein as an Optical Sensor for Spatiotemporal Mapping of pH Inside Porous Matrices.

Science.gov (United States)

Consolati, Tanja; Bolivar, Juan M; Petrasek, Zdenek; Berenguer, Jose; Hidalgo, Aurelio; Guisán, Jose M; Nidetzky, Bernd

2018-02-28

The pH is fundamental to biological function and its measurement therefore crucial across all biosciences. Unlike homogenous bulk solution, solids often feature internal pH gradients due to partition effects and confined biochemical reactions. Thus, a full spatiotemporal mapping for pH characterization in solid materials with biological systems embedded in them is essential. In here, therefore, a fully biocompatible methodology for real-time optical sensing of pH within porous materials is presented. A genetically encoded ratiometric pH sensor, the enhanced superfolder yellow fluorescent protein (sYFP), is used to functionalize the internal surface of different materials, including natural and synthetic organic polymers as well as silica frameworks. By using controlled, tailor-made immobilization, sYFP is homogenously distributed within these materials and so enables, via self-referenced imaging analysis, pH measurements in high accuracy and with useful spatiotemporal resolution. Evolution of internal pH is monitored in consequence of a proton-releasing enzymatic reaction, the hydrolysis of penicillin by a penicillin acylase, taking place in solution or confined to the solid surface of the porous matrix. Unlike optochemical pH sensors, which often interfere with biological function, labeling with sYFP enables pH sensing without altering the immobilized enzyme's properties in any of the materials used. Fast response of sYFP to pH change permits evaluation of biochemical kinetics within the solid materials. Thus, pH sensing based on immobilized sYFP represents a broadly applicable technique to the study of biology confined to the internally heterogeneous environment of solid matrices.

Thermomechanics of solid materials with application to the Gurson-Tvergaard material model

Energy Technology Data Exchange (ETDEWEB)

Santaoja, K. [VTT Manufacturing Technology, Espoo (Finland). Materials and Structural Integrity

1997-12-31

The elastic-plastic material model for porous material proposed by Gurson and Tvergaard is evaluated. First a general description is given of constitutive equations for solid materials by thermomechanics with internal variables. The role and definition of internal variables are briefly discussed and the following definition is given: The independent variables present (possibly hidden) in the basic laws for thermomechanics are called controllable variables. The other independent variables are called internal variables. An internal variable is shown always to be a state variable. This work shows that if the specific dissipation function is a homogeneous function of degree one in the fluxes, a description for a time-independent process is obtained. When damage to materials is evaluated, usually a scalar-valued or tensorial variable called damage is introduced in the set of internal variables. A problem arises when determining the relationship between physically observable weakening of the material and the value for damage. Here a more feasible approach is used. Instead of damage, the void volume fraction is inserted into the set of internal variables. This allows use of an analytical equation for description of the mechanical weakening of the material. An extension to the material model proposed by Gurson and modified by Tvergaard is derived. The derivation is based on results obtained by thermomechanics and damage mechanics. The main difference between the original Gurson-Tvergaard material model and the extended one lies in the definition of the internal variable `equivalent tensile flow stress in the matrix material` denoted by {sigma}{sup M}. Using classical plasticity theory, Tvergaard elegantly derived an evolution equation for {sigma}{sup M}. This is not necessary in the present model, since damage mechanics gives an analytical equation between the stress tensor {sigma} and {sigma}M. Investigation of the Clausius-Duhem inequality shows that in compression

Thermomechanics of solid materials with application to the Gurson-Tvergaard material model

International Nuclear Information System (INIS)

Santaoja, K.

1997-01-01

The elastic-plastic material model for porous material proposed by Gurson and Tvergaard is evaluated. First a general description is given of constitutive equations for solid materials by thermomechanics with internal variables. The role and definition of internal variables are briefly discussed and the following definition is given: The independent variables present (possibly hidden) in the basic laws for thermomechanics are called controllable variables. The other independent variables are called internal variables. An internal variable is shown always to be a state variable. This work shows that if the specific dissipation function is a homogeneous function of degree one in the fluxes, a description for a time-independent process is obtained. When damage to materials is evaluated, usually a scalar-valued or tensorial variable called damage is introduced in the set of internal variables. A problem arises when determining the relationship between physically observable weakening of the material and the value for damage. Here a more feasible approach is used. Instead of damage, the void volume fraction is inserted into the set of internal variables. This allows use of an analytical equation for description of the mechanical weakening of the material. An extension to the material model proposed by Gurson and modified by Tvergaard is derived. The derivation is based on results obtained by thermomechanics and damage mechanics. The main difference between the original Gurson-Tvergaard material model and the extended one lies in the definition of the internal variable 'equivalent tensile flow stress in the matrix material' denoted by σ M . Using classical plasticity theory, Tvergaard elegantly derived an evolution equation for σ M . This is not necessary in the present model, since damage mechanics gives an analytical equation between the stress tensor σ and σM. Investigation of the Clausius-Duhem inequality shows that in compression, states occur which are not

PREFACE: 5th International Conference on Materials and Applications for Sensors and Transducers (IC-MAST2015)

Science.gov (United States)

Hristoforou, E.; Vlachos, D. S.; Giouroudi, I.; Kar-Narayan, S.; Potirakis, S.

2016-03-01

The 5th International Conference on Materials and Applications for Sensors and Transducers, Mykonos island, Greece, hosted about 110 oral and poster papers and more than 90 participants. IC-MAS, as an international annual conference which tries to meet the needs for various types of sensors, particularly those which may be manufactured by low cost methods (i.e. hybrid sensors, smart specialization devices, particular applications not necessarily requiring integrated micro-nano technologies), covering all types of materials and physical effects, appears to be a necessity. IC-MAST has been established as a high quality international conference by: I. Gathering together multinational researchers from all over the world, working in different materials for sensors and transducers and technical applications of sensors, but also in some cases in the management of the data coming from sensors and transducers. The careful selection of the conference place (like Aegean Sea, Budapest, Prague, Bilbao, Mykonos etc) allows for enjoying the local hospitality and sightseeing. II. Emphasizing in hybrid sensors and smart specialization devices produced by inexpensive methods, without excluding of course micro-nano technology, from all kinds of solid state, liquid and gaseous materials, as well as in particular transducer applications (design and development, as well as use of sensing data) III. Innovatively implementing the Virtual Paper Concept, allowing for large impact of research works presented in the conference by authors who either have no time or no funding support for visiting a conference; this year more than 12 virtual papers are presented in the 5th IC MAST, following a standardized procedure via the our robust and reliable Conference Site (www.icmast.net!) > IV. Allowing for lengthy technical and managerial discussions in terms of sensor, material and instrumentation development; furthermore, the different research groups gathered together are offered the particular

Effect of Tooling Material on the Internal Surface Quality of Ti6Al4V Parts Fabricated by Hot Isostatic Pressing

Science.gov (United States)

Cai, Chao; Song, Bo; Wei, Qingsong; Yan, Wu; Xue, Pengju; Shi, Yusheng

2017-01-01

For the net-shape hot isostatic pressing (HIP) process, control of the internal surface roughness of as-HIPped parts remains a challenge for practical engineering. To reveal the evolution mechanism of the internal surface of the parts during the HIP process, the effect of different tooling materials (H13, T8, Cr12 steel, and graphite) as internal cores on the interfacial diffusion and surface roughness was systematically studied.

Contribution to internal pressure and flammable gas concentration in RAM [radioactive material] transport packages

International Nuclear Information System (INIS)

Warrant, M.M.; Brown, N.

1989-01-01

Various facilities in the US generate wastes contaminated with transuranic (TRU) isotopes (such as plutonium and americium) that decay primarily by emission of alpha particles. The waste materials consist of a wide variety of commercially available plastics, paper, cloth, and rubber; concreted or sludge wastes containing water; and metals, glass, and other solid inorganic materials. TRU wastes that have surface dose rates of 200 mrem/hr or less are typically packaged in plastic bags placed inside metal drums or boxes that are vented through high efficiency particulate air (HEPA) filters. These wastes are to be transported from waste generation or storage sites to the Waste Isolation Pilot Plant (WIPP) in the TRUPACT-II, a Type B package. Radiolysis of organic wastes or packaging materials, or wastes containing water generates gas which may be flammable or simply contribute to the internal pressure of the radioactive material (RAM) transport package. This paper discusses the factors that affect the amount and composition of this gas, and summarizes maximum radiolytic G values (number of molecules produced per 100 eV absorbed energy) found in the technical literature for many common materials. These G values can be used to determine the combination of payload materials and decay heats that are safe for transport. G values are established for categories of materials, based on chemical functional groups. It is also shown using transient diffusion and quasi-equilibrium statistical mechanics methods that hydrogen, if generated, will not stratify at the top of the transport package void space. 9 refs., 1 tab

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

Energy Technology Data Exchange (ETDEWEB)

1984-06-01

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

Extended abstracts of the 8. international symposium on new materials and nano-materials for electrochemical systems : emerging trends and challenges in new materials development for sustainable energy and environment

International Nuclear Information System (INIS)

Savadogo, O.; Ma, Z.F.

2010-01-01

This conference provided a forum to highlight the advances made in the development of new materials and nano-materials for electrochemical systems, including fuel cells. Electrochemical energy system devices have the potential to provide new applications for high power mobile systems as an alternative to internal combustion engines. They also have the potential for applications in hand-held personal electronic devices, uninterrupted power supply and auxiliary power supply. However, additional advances in unit cell material and design are still needed before mass production of fuel cells can begin. Cost, reliability, service life, electrode performance and power density are among the technical challenges facing commercialization. In addition to a plenary and general session, the sessions of the conference were entitled: low temperature fuel cells; high temperature fuel cells; advanced secondary rechargeable batteries; hydrogen production and storage; electrochemical supercapacitors; and poster session. All 166 presentations at this conference have been catalogued separately for inclusion in this database

PREFACE: International Scientific Conference of Young Scientists: Advanced Materials in Construction and Engineering (TSUAB2014)

Science.gov (United States)

Kopanitsa, Natalia O.

2015-01-01

In October 15-17, 2014 International Scientific Conference of Young Scientists: Advanced Materials in Construction and Engineering (TSUAB2014) took place at Tomsk State University of Architecture and Building (Tomsk, Russia). The Conference became a discussion platform for researchers in the fields of studying structure and properties of advanced building materials and included open lectures of leading scientists and oral presentations of master, postgraduate and doctoral students. A special session was devoted to reports of school children who further plan on starting a research career. The Conference included an industrial exhibition where companies displayed the products and services they supply. The companies also gave presentations of their products within the Conference sessions.

[International Panel on 14 MeV Intense Neutron Source Based on Accelerators for Fusion Materials Study

International Nuclear Information System (INIS)

Thoms, K.R.; Wiffen, F.W.

1991-01-01

Both travelers were members of a nine-person US delegation that participated in an international workshop on accelerator-based 14 MeV neutron sources for fusion materials research hosted by the University of Tokyo. Presentations made at the workshop reviewed the technology developed by the FMIT Project, advances in accelerator technology, and proposed concepts for neutron sources. One traveler then participated in the initial meeting of the IEA Working Group on High Energy, High Flux Neutron Sources in which efforts were begun to evaluate and compare proposed neutron sources; the Fourth FFTF/MOTA Experimenters' Workshop which covered planning and coordination of the US-Japan collaboration using the FFTF reactor to irradiate fusion reactor materials; and held discussions with several JAERI personnel on the US-Japan collaboration on fusion reactor materials

The future Jules Horowitz material testing reactor: An opportunity for developing international collaborations on a major European irradiation infrastructure

International Nuclear Information System (INIS)

Parrat, D.; Bignan, G.; Maugard, B.; Gonnier, C.; Blandin, C.

2015-01-01

Development process of a fuel product or a nuclear material before using at an industrial scale in a power reactor ranges from characterization of the material itself under neutronic flux up to its qualification in accidental conditions. Irradiations in Material Testing Reactors (MTRs) are in practice the basis of the whole process, in complement of prediction capabilities gained by modelling. Dedicated experimental reactors play also an important complementary role for some specific integral tests (e.g. RIA tests). Irradiations of precursors in power reactors are often limited to products which present a slight design evolution compare to the standard product or are implemented for further tests when a statistical approach is useful for defining a safety criterion. However European MTR park status is characterized by ageing infrastructures, which could cause operational issues in coming years, either on technological or on safety point of views. Moreover some specific supplies related to the public demand could be strongly affected (e.g. radiopharmaceutical targets). To avoid a lack in irradiation capacity offer at European level, CEA launched the Jules Horowitz Material Testing Reactor (JHR) international program, in the frame of a Consortium gathering also EDF (FR), AREVA (FR), European Commission (EU), SCK.CEN (BE), VTT (FI), CIEMAT (SP), STUDSVIK (SE), UJV (CZ), NNL (UK), IAEC (IL), DAE (IN) and as associated partnership: JAEA (JP). Some institutions in this list are themselves the flagship of a national Consortium. Discussions for enlarging participation are on-going with other countries, as JHR Consortium is open to new member entrance until JHR completion. The Jules Horowitz Material Testing Reactor (JHR MTR) is under construction at CEA Cadarache in southern France and will be an important international User Facility for R&D in support to the nuclear industry, research centres, regulatory bodies and TSO, and academic institutions. It represents a unique

Book of abstracts of the 3rd International conference and the 3rd International School for young scientists Interaction of hydrogen isotopes with structural materials. IHISM-07

International Nuclear Information System (INIS)

2007-01-01

The book involves abstracts of presentations at the 3rd International Conference and the 3rd International School for Young Scientists Interaction of Hydrogen Isotopes with Structural Materials (IHISM-07). The activities of Russian and foreign scientific centers associated with the use of hydrogen isotopes in power engineering, national economy and basic research are considered. The presentations cover the following areas: kinetics and interaction between hydrogen isotopes and solids including effects of radiogenic helium accumulation, hydrides and hydride transformations; structural transformations and mechanical properties; equipment and research techniques [ru

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

International Nuclear Information System (INIS)

2001-01-01

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

Materials Science Research Rack Onboard the International Space Station Hardware and Operations

Science.gov (United States)

Lehman, John R.; Frazier, Natalie C.; Johnson, Jimmie

2012-01-01

The Materials Science Research Rack (MSRR) is a research facility developed under a cooperative research agreement between NASA and ESA for materials science investigations on the International Space Station (ISS). MSRR was launched on STS-128 in August 2009, and is currently installed in the U.S. Destiny Laboratory Module. Since that time, MSRR has performed virtually flawlessly, logging more than 620 hours of operating time. The MSRR accommodates advanced investigations in the microgravity environment on the ISS for basic materials science research in areas such as solidification of metals and alloys. The purpose is to advance the scientific understanding of materials processing as affected by microgravity and to gain insight into the physical behavior of materials processing. MSRR allows for the study of a variety of materials including metals, ceramics, semiconductor crystals, and glasses. Materials science research benefits from the microgravity environment of space, where the researcher can better isolate chemical and thermal properties of materials from the effects of gravity. With this knowledge, reliable predictions can be made about the conditions required on Earth to achieve improved materials. MSRR is a highly automated facility with a modular design capable of supporting multiple types of investigations. Currently the NASA-provided Rack Support Subsystem provides services (power, thermal control, vacuum access, and command and data handling) to the ESA developed Materials Science Laboratory (MSL) which accommodates interchangeable Furnace Inserts (FI). Two ESA-developed FIs are presently available on the ISS: the Low Gradient Furnace (LGF) and the Solidification and Quenching Furnace (SQF). Sample-Cartridge Assemblies (SCAs), each containing one or more material samples, are installed in the FI by the crew and can be processed at temperatures up to 1400 C. Once an SCA is installed, the experiment can be run by automatic command or science conducted via

Effectiveness of the International Phytosanitary Standard ISPM No. 15 on reducing wood borer infestation rates in wood packaging material entering the United States

Science.gov (United States)

Robert A. Haack; Kerry O. Britton; Eckelhard G. Brockerhoff; Joseph F. Cavey; Lynn J. Garrett; Mark Kimberley; Frank Lowenstein; Amelia Nuding; Lars J. Olson; James Tumer; Kathryn N. Vasilaky

2014-01-01

Numerous bark- and wood-infesting insects have been introduced to new countries by international trade where some have caused severe environmental and economic damage. Wood packaging material (WPM), such as pallets, is one of the high risk pathways for the introduction of wood pests. International recognition of this risk resulted in adoption of International Standards...

Plasma-materials interaction issues for the International Thermonuclear Experimental Reactor (ITER)

International Nuclear Information System (INIS)

Cohen, S.A.; Werley, K.A.

1992-02-01

Analysis of proposed operating scenarios for the International Thermonuclear Experimental Reactor has yielded predictions for the power and particle fluxes onto the material surfaces facing the plasma. The particles, mostly deuterium, tritium, and helium ions, would have energies in the range of 50--2000 eV and fluxes up to 5 x 10 23 /m 2 s. Lower fluxes of multi-MeV electrons and alpha particles may also strike the plasma-facing surfaces, primarily during transient events. The peak power fluxes onto the plasma-facing surfaces during normal operation are expected to be 5--100 MW/m 2 , but much higher during transient events. At the extreme conditions expected for steady-state operation, commonly used heat-removal structures are unable to withstand either the high sputter erosion rates or power loads. To reduce the time-averaged power flux, active control of the plasma position is specified to sweep the plasma heat load across larger areas of plasma-facing components. However, the cyclic heat load creates fatigue lifetime problems. Solutions to these lifetime and reliability problems by (1) changes in machine design and operation, (2) redeposition mechanisms, and (3) changes in materials, will be discussed. A proposed accelerated-life test facility for prototype divertor plate development is described

Investigation of high flux test module for the international fusion materials irradiation facilities (IFMIF)

International Nuclear Information System (INIS)

Miyashita, Makoto; Sugimoto, Masayoshi; Yutani, Toshiaki

2007-03-01

This report describes investigation on structure of a high neutron flux test module (HFTM) for the International Fusion Materials Irradiation Facilities (IFMIF). The HFTM is aimed for neutron irradiation of a specimen in a high neutron flux domain of the test cell for irradiation ground of IFMIF. We investigated the overall structure of the HFTM that was able to include specimens in a rig and thermocouple arrangement, an interface of control signal and support structure. Moreover, pressure and the amount of the bend in the module vessel (a rectangular section pressure vessel) were calculated. The module vessel did a rectangular section from limitation of a high neutron flux domain. Also, we investigated damage of thermocouples under neutron irradiation, which was a temperature sensor of irradiation materials temperature control demanded high precision. Based on these results, drawings on the HTFM structure. (author)

Television Traffic: A One-Way Street? A Survey and Analysis of the International Flow of Television Programme Material. Reports and Papers on Mass Communication No. 70.

Science.gov (United States)

Nordenstreng, Kaarle; Varis, Tapio

An international inventory was made to determine the composition of television programs, particularly from the point of view of program material exported to a country outside. A survey was also made of the international networks for sales and exchanges of program material for broadcast. A report of these studies includes the scope and methods of…

The application of radiochronometry during the 4th collaborative materials exercise of the nuclear forensics international technical working group (ITWG)

OpenAIRE

KRISTO M.; WILLIAMS ROSS; GAFFNEY AMY; KAYZAR-BOGGS THERESA; SCHOZMAN KERRI; LAGERKVIST P.; VESTERLUND ANNA; RAMEBÄCK HENRIK; NELWAMONDO AUBREY; KOTZE DEON; SONG KYUSEOK; LIM SANG HO; HAN SUN-HO; LEE CHI-GYU; OKUBO AYAKO

2018-01-01

In a recent international exercise, 10 international nuclear forensics laboratories successfully performed radiochronometry on three low enriched uranium oxide samples, providing 12 analytical results using three different parent-daughter pairs serving as independent chronometers. The vast majority of the results were consistent with one another and consistent with the known processing history of the materials. In general, for these particular samples, mass spectrometry gave more ...

The role of certified reference materials in material control and accounting

International Nuclear Information System (INIS)

Turel, S.P.

1979-01-01

One way of providing an adequate material control and accounting system for the nuclear fuel cycle is to calculate material unaccounted for (MUF) after a physical inventory and to compare the limit of error of the MUF value (LEMUF) against prescribed criteria. To achieve a meaningful LEMUF, a programme for the continuing determination of systematic and random errors is necessary. Within this programme it is necessary to achieve traceability of all Special Nuclear Material (SNM) control and accounting measurements to an International/National Measurement System by means of Certified Reference Materials. SNM measurements for control and accounting are made internationally on a great variety of materials using many diverse measurement procedures by a large number of facilities. To achieve valid overall accountability over this great variety of measurements there must be some means of relating all these measurements and their uncertainties to each other. This is best achieved by an International/National Measurement System (IMS/NMS). To this end, all individual measurement systems must be compatible to the IMS/NMS and all measurement results must be traceable to appropriate international/national Primary Certified Reference Materials. To obtain this necessary compatibility for any given SNM measurement system, secondary certified reference materials or working reference materials are needed for every class of SNM and each type of measurement system. Ways to achieve ''traceability'' and the various types of certified reference material are defined and discussed in this paper. (author)

Supervision of nuclear material in the Federal Republic of Germany by the Commission of the European Communities (Euratom) and the International Atomic Energy Organisation (IAEO)

International Nuclear Information System (INIS)

Brueckner, C.

1979-01-01

Since the fifties Euratom has controlled nuclear material in the Federal Republic of Germany. When the verification agreement came into force in the treaty on the non-proliferation of atomic weapons in February 1977, the International Atomic Energy Organisation (IAEO) has commenced the supervision of nuclear material in German nuclear energy installations. The author describes the basic principle of the supervision and the possible effects on the installations. In addition, he also deals with the discussions which have flared up about the international supervision of nuclear material, and indicates possible future developments. (orig.) [de

Proceedings of the first international conference on indium phosphide and related materials for advanced electronic and optical devices

International Nuclear Information System (INIS)

Singh, R.; Messick, L.J.

1989-01-01

This book contains the proceedings of the first international conference on indium phosphide and related materials for advanced electronic and optical devices. Topics covered include: Growth and characterization of bulk and epitaxial films, Passivation technology, Processing technology, High speed optoelectronic integrated circuits, and Solar cells

Control and Management of Radioactive Material Inadvertently Incorporated into Scrap Metal. Proceedings of an International Conference

International Nuclear Information System (INIS)

2011-01-01

Radioactive substances can become associated with scrap metal in various ways and if not discovered they can be incorporated into steel and non-ferrous metals through the melting process. This can cause health hazards as well as environmental concerns and there can be serious commercial implications. Numerous incidents have occurred in recent years involving the discovery of radioactive substances in scrap metal and, in some cases, in metal from the melting process. These incidents have proved to be very costly in relation to the recovery and cleanup operations required but also in terms of the potential loss of confidence of the industry in scrap metal as a resource. This has led the scrap metal industry to seek ways of managing the problem. In most countries, shipments of scrap metal are monitored but at different points in the distribution chain and to different extents and efficiencies. As yet, only limited efforts towards unifying and harmonizing monitoring strategies and methods in the context of scrap metal have been made at the international level. The Conference was organized into five sessions: the global perspective, national policies and strategies, compliance with radiological criteria, management of incidents with contaminated scrap metal, and improving confidence and protecting the interests of stakeholders. The aim of the first session was to present the views and perspectives of the different organizations concerned with radioactive material in scrap metal, scrap metal recycling, steel making, radiation source security and safety and international trade and economics. The second session covered some of the national policies and strategies being used to address the control of radioactive material that has been inadvertently incorporated into scrap metal were presented. In addition to the oral presentations, contributions describing the situation in many countries of the world in the form of posters were displayed. The many posters reporting national

Control and Management of Radioactive Material Inadvertently Incorporated into Scrap Metal. Proceedings of an International Conference

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-15

Radioactive substances can become associated with scrap metal in various ways and if not discovered they can be incorporated into steel and non-ferrous metals through the melting process. This can cause health hazards as well as environmental concerns and there can be serious commercial implications. Numerous incidents have occurred in recent years involving the discovery of radioactive substances in scrap metal and, in some cases, in metal from the melting process. These incidents have proved to be very costly in relation to the recovery and cleanup operations required but also in terms of the potential loss of confidence of the industry in scrap metal as a resource. This has led the scrap metal industry to seek ways of managing the problem. In most countries, shipments of scrap metal are monitored but at different points in the distribution chain and to different extents and efficiencies. As yet, only limited efforts towards unifying and harmonizing monitoring strategies and methods in the context of scrap metal have been made at the international level. The Conference was organized into five sessions: the global perspective, national policies and strategies, compliance with radiological criteria, management of incidents with contaminated scrap metal, and improving confidence and protecting the interests of stakeholders. The aim of the first session was to present the views and perspectives of the different organizations concerned with radioactive material in scrap metal, scrap metal recycling, steel making, radiation source security and safety and international trade and economics. The second session covered some of the national policies and strategies being used to address the control of radioactive material that has been inadvertently incorporated into scrap metal were presented. In addition to the oral presentations, contributions describing the situation in many countries of the world in the form of posters were displayed. The many posters reporting national

Techniques and materials for internal water curing of concrete

DEFF Research Database (Denmark)

Jensen, Ole Mejlhede; Lura, Pietro

2006-01-01

This paper gives an overview of different techniques for incorporation of internal curing water in concrete. Internal water curing can be used to mitigate self-desiccation and selfdesiccation shrinkage. Some concretes may need 50 kg/m3 of internal curing water for this purpose. The price...

Materials International Space Station Experiment (MISSE) 5 Developed to Test Advanced Solar Cell Technology Aboard the ISS

Science.gov (United States)

Wilt, David M.

2004-01-01

The testing of new technologies aboard the International Space Station (ISS) is facilitated through the use of a passive experiment container, or PEC, developed at the NASA Langley Research Center. The PEC is an aluminum suitcase approximately 2 ft square and 5 in. thick. Inside the PEC are mounted Materials International Space Station Experiment (MISSE) plates that contain the test articles. The PEC is carried to the ISS aboard the space shuttle or a Russian resupply vehicle, where astronauts attach it to a handrail on the outer surface of the ISS and deploy the PEC, which is to say the suitcase is opened 180 deg. Typically, the PEC is left in this position for approximately 1 year, at which point astronauts close the PEC and it is returned to Earth. In the past, the PECs have contained passive experiments, principally designed to characterize the durability of materials subjected to the ultraviolet radiation and atomic oxygen present at the ISS orbit. The MISSE5 experiment is intended to characterize state-of-art (SOA) and beyond photovoltaic technologies.

The Structuring of Shared Voluntary Standards in the U.S. Semiconductor Industry: Communicating to Reach Agreement.

Science.gov (United States)

Browning, Larry D.; Beyer, Janice M.

1998-01-01

Contributes to scholarship on organizational communication by tracing how voluntary cooperative standards were developed for the semiconductor industry through reflexive communication processes initiated by the SEMATECH consortium. Analyzes seven pivotal incidents that show how increased communication produced new provinces of meaning, actions,…

Encountering Materiality

DEFF Research Database (Denmark)

Svabo, Connie

2016-01-01

DHT researcher Connie Svabo and artist Charlotte Grum did a joint performance presentation titled Becoming Sheep, Becoming Animal at the international conference Encountering Materiality – Transdisciplinary Conversations, held in Geneve, Schwitzerland, June 23-25 2016.......DHT researcher Connie Svabo and artist Charlotte Grum did a joint performance presentation titled Becoming Sheep, Becoming Animal at the international conference Encountering Materiality – Transdisciplinary Conversations, held in Geneve, Schwitzerland, June 23-25 2016....

PREFACE: 2nd International Conference on Competitive Materials and Technological Processes (IC-CMTP2)

Science.gov (United States)

László, Gömze A.

2013-12-01

Competitiveness is one of the most important factors in our life and it plays a key role in the efficiency both of organizations and societies. The more scientifically supported and prepared organizations develop more competitive materials with better physical, chemical and biological properties and the leading companies apply more competitive equipment and technology processes. The aims of the 2nd International Conference on Competitive Materials and Technology Processes (ic-cmtp2) are the following: Promote new methods and results of scientific research in the fields of material, biological, environmental and technology sciences; Change information between the theoretical and applied sciences as well as technical and technological implantations. Promote the communication between the scientist of different nations, countries and continents. Among the major fields of interest are materials with extreme physical, chemical, biological, medical, thermal, mechanical properties and dynamic strength; including their crystalline and nano-structures, phase transformations as well as methods of their technological processes, tests and measurements. Multidisciplinary applications of materials science and technological problems encountered in sectors like ceramics, glasses, thin films, aerospace, automotive and marine industry, electronics, energy, construction materials, medicine, biosciences and environmental sciences are of particular interest. In accordance to the program of the conference ic-cmtp2, more than 250 inquiries and registrations from different organizations were received. Researchers from 36 countries in Asia, Europe, Africa, North and South America arrived at the venue of conference. Including co-authors, the research work of more than 500 scientists are presented in this volume. Professor Dr Gömze A László Chair, ic-cmtp2 The PDF also contains lists of the boards, session chairs and sponsors.

International Scientific Conference on 'Radiation-Thermal Effects and Processes in Inorganic Materials'

International Nuclear Information System (INIS)

2015-01-01

The International Scientific Conference on 'Radiation-Thermal Effects and Processes in Inorganic Materials' is a traditional representative forum devoted to the discussion of fundamental problems of radiation physics and its technical applications. The first nine conferences were held four times in Tomsk, then in Ulan-Ude (Russia), Bishkek (Kyrgyzstan), Tashkent (Uzbekistan), Sharm El Sheikh (Egypt), and the island of Cyprus. The tenth conference was held in Tomsk, Russia. The program of the Conference covers a wide range of technical areas and modern aspects of radiation physics, its applications and related matters. Topics of interest include, but are not limited to: • Physical and chemical phenomena in inorganic materials in radiation, electrical and thermal fields; • Research methods and equipment modification states and properties of materials; • Technologies and equipment for their implementation; • The use of radiation-thermal processes in nanotechnology; • Adjacent to the main theme of the conference issues The conference was attended by leading scientists from countries near and far abroad who work in the field of radiation physics of solid state and of radiation material science. The School-Conference of Young Scientists was held during the conference. The event was held with the financial support of the Russian Foundation for Basic Research, projects № 14-38-10210 and № 14-02-20376. (introduction)

PATRAM '83: 7th international symposium on packaging and transportation of radioactive materials

International Nuclear Information System (INIS)

1983-01-01

Papers were presented at the following sessions: international regulations; materials, fracture toughness of ferritic steels; risk analysis techniques; storage in packagings; packaging design considerations; monolithic cast iron casks; risk analysis; facility/transportation system interface; research and development programs; UF 6 packagings; national regulations; transportation operations and traffic; containment, seals, and leakage; radiation risk experience; emergency response; structural modeling and testing; transportation system planning; institutional issues and public response; packaging systems; thermal analysis and testing; systems analysis; structural analyses; quality assurance; packaging and transportation systems; physical protection; criticality and shielding; transportation operations and experience; standards; shock absorber technology; and information and training for regulatory compliance. Individual summaries are title listed

PREFACE: 12th Russia/CIS/Baltic/Japan Symposium on Ferroelectricity and 9th International Conference on Functional Materials and Nanotechnologies (RCBJSF-2014-FM&NT)

Science.gov (United States)

Sternberg, Andris; Grinberga, Liga; Sarakovskis, Anatolijs; Rutkis, Martins

2015-03-01

The joint International Symposium RCBJSF-2014-FM&NT successfully has united two international events - 12th Russia/CIS/Baltic/Japan Symposium on Ferroelectricity (RCBJSF-12) and 9th International Conference Functional Materials and Nanotechnologies (FM&NT-2014). The RCBJSF symposium is a continuation of series of meetings on ferroelectricity, the first of which took place in Novosibirsk (USSR) in 1976. FM&NT conferences started in 2006 and have been organized by Institute of Solid State Physics, University of Latvia in Riga. In 2012 the International program committee decided to transform this conference into a traveling Baltic State conference and the FM&NT-2013 was organized by the Institute of Physics, University of Tartu, Estonia. In 2014 the joint international symposium RCBJSF-2014-FM&NT was organized by the Institute of Solid State Physics, University of Latvia and was part of Riga - 2014, the European Capital of Culture event. The purpose of the joint Symposium was to bring together scientists, students and high-level experts in solid state physics, materials science, engineering and related disciplines. The number of the registered participants from 26 countries was over 350. During the Symposium 128 high quality scientific talks (5 plenary, 42 invited, 81 oral) and over 215 posters were presented. All presentations were divided into 4 parallel sessions according to 4 main topics of the Symposium: Ferroelectricity, including ferroelectrics and multiferroics, pyroelectrics, piezoelectrics and actuators, integrated ferroelectrics, relaxors, phase transitions and critical phenomena. Multifunctional Materials, including theory, multiscale and multiphenomenal material modeling and simulation, advanced inorganic, organic and hybrid materials. Nanotechnologies, including progressive methods, technologies and design for production, investigation of nano- particles, composites, structures, thin films and coatings. Energy, including perspective materials and

The effects of radiations on materials for core internals of PWRs: EDF-CEA-Framatome joint research programme

International Nuclear Information System (INIS)

Mathan, N. de; Buisine, D.; Goltrant, O.; Dubuisson, P.; Scott, P.; Deydier, D.; Trenty, A.

1998-01-01

The effects of neutron irradiation on materials for the core internals of PWRs (austenitic stainless steels) are potentially a significant economic and regulatory concern for EDF. The maintenance strategy for EDF relies primarily on in-service inspection, safety analysis and characterization of materials irradiated in-service. In addition, to anticipate likely future behaviour of highly irradiated materials, EDF has initiated, in collaboration with CEA and Framatome, a large R and D programme designed to (i) evaluate the effects of neutron irradiation on mechanical properties and stress corrosion cracking sensitivity (IASCC), and (ii) identify possible replacement materials. The programme, currently in progress, involves mechanical tests (tensile, fracture toughness, irradiation creep), stress corrosion cracking tests (in flux and out of flux) and metallurgical examinations. The test materials are being irradiated in several experimental reactors in France and Russia up to PWR-related end of life doses (∼ 80 dpa) at several PWR-relevant irradiation temperatures (300-400 deg. C). The presentation will describe the objectives and early results of this ongoing R and D programme. (author)

Review of the International Atomic Energy Agency International database on reactor pressure vessel materials and US Nuclear Regulatory Commission/Oak Ridge National Laboratory embrittlement data base

International Nuclear Information System (INIS)

Wang, J.A.; Kam, F.B.K.

1998-02-01

The International Atomic Energy Agency (IAEA) has supported neutron radiation effects information exchange through meetings and conferences since the mid-1960s. Through an International Working Group on Reliability of Reactor Pressure Components, information exchange and research activities were fostered through the Coordinated Research Program (CRP) sponsored by the IAEA. The final CRP meeting was held in November 1993, where it was recommended that the IAEA coordinate the development of an International Database on Reactor Pressure Vessel Material (IDRPVM) as the first step in generating an International Database on Aging Management. The purpose of this study was to provide special technical assistance to the NRC in monitoring and evaluating the IAEA activities in developing the IAEA IDRPVM, and to compare the IDRPVM with the Nuclear Regulatory Commission (NRC) - Oak Ridge National Laboratory (ORNL) Power Reactor Embrittlement Data Base (PR-EDB) and provide recommendations for improving the PR-EDB. A first test version of the IDRPVM was distributed at the First Meeting of Liaison Officers to the IAEA IDRPVM, in November 1996. No power reactor surveillance data were included in this version; the testing data were mainly from CRP Phase III data. Therefore, because of insufficient data and a lack of power reactor surveillance data received from the IAEA IDRPVM, the comparison is made based only on the structure of the IDRPVM. In general, the IDRPVM and the EDB have very similar data structure and data format. One anticipates that because the IDRPVM data will be collected from so many different sources, quality assurance of the data will be a difficult task. The consistency of experimental test results will be an important issue. A very wide spectrum of material characteristics of RPV steels and irradiation environments exists among the various countries. Hence the development of embrittlement prediction models will be a formidable task. 4 refs., 2 figs., 4 tabs

PREFACE: 3rd International Workshop on Materials Analysis and Processing in Magnetic Fields (MAP3)

Science.gov (United States)

Sakka, Yoshio; Hirota, Noriyuki; Horii, Shigeru; Ando, Tsutomu

2009-07-01

The 3rd International Workshop on Materials Analysis and Processing in Materials Fields (MAP3) was held on 14-16 May 2008 at the University of Tokyo, Japan. The first was held in March 2004 at the National High Magnetic Field Laboratory in Tallahassee, USA. Two years later the second took place in Grenoble, France. MAP3 was held at The University of Tokyo International Symposium, and jointly with MANA Workshop on Materials Processing by External Stimulation, and JSPS CORE Program of Construction of the World Center on Electromagnetic Processing of Materials. At the end of MAP3 it was decided that the next MAP4 will be held in Atlanta, USA in 2010. Processing in magnetic fields is a rapidly expanding research area with a wide range of promising applications in materials science. MAP3 focused on the magnetic field interactions involved in the study and processing of materials in all disciplines ranging from physics to chemistry and biology: Magnetic field effects on chemical, physical, and biological phenomena Magnetic field effects on electrochemical phenomena Magnetic field effects on thermodynamic phenomena Magnetic field effects on hydrodynamic phenomena Magnetic field effects on crystal growth Magnetic processing of materials Diamagnetic levitation Magneto-Archimedes effect Spin chemistry Application of magnetic fields to analytical chemistry Magnetic orientation Control of structure by magnetic fields Magnetic separation and purification Magnetic field-induced phase transitions Materials properties in high magnetic fields Development of NMR and MRI Medical application of magnetic fields Novel magnetic phenomena Physical property measurement by Magnetic fields High magnetic field generation> MAP3 consisted of 84 presentations including 16 invited talks. This volume of Journal of Physics: Conference Series contains the proceeding of MAP3 with 34 papers that provide a scientific record of the topics covered by the conference with the special topics (13 papers) in

Verification of excess defense material

International Nuclear Information System (INIS)

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

1997-01-01

The international community in the post-Cold War period has expressed an interest in the International Atomic Energy Agency (IAEA) using its expertise in support of the arms control and disarmament process in unprecedented ways. The pledges of the US and Russian presidents to place excess defense materials under some type of international inspections raises the prospect of using IAEA safeguards approaches for monitoring excess materials, which include both classified and unclassified materials. Although the IAEA has suggested the need to address inspections of both types of materials, the most troublesome and potentially difficult problems involve approaches to the inspection of classified materials. The key issue for placing classified nuclear components and materials under IAEA safeguards is the conflict between these traditional IAEA materials accounting procedures and the US classification laws and nonproliferation policy designed to prevent the disclosure of critical weapon-design information. Possible verification approaches to classified excess defense materials could be based on item accountancy, attributes measurements, and containment and surveillance. Such approaches are not wholly new; in fact, they are quite well established for certain unclassified materials. Such concepts may be applicable to classified items, but the precise approaches have yet to be identified, fully tested, or evaluated for technical and political feasibility, or for their possible acceptability in an international inspection regime. Substantial work remains in these areas. This paper examines many of the challenges presented by international inspections of classified materials

Regulation of naturally occurring radioactive material (NORM) -- an international perspective

International Nuclear Information System (INIS)

Davis, M.W.

1997-01-01

Naturally Occurring Radioactive Material (NORM) was first recognized as a potential problem as long ago as 1904 in the oil fields of Canada. NORM later became an issue in the North Sea oil and gas production facilities in the early 1980's and became more widely recognized in the United States in 1986 during a routine well workover in the state of Mississippi. NORM contamination of oil and gas industry production equipment has since been identified world wide. The United States, including Alaska and the Gulf of Mexico region, the North Sea region, the United Kingdom, Canada, Australia and several Middle Eastern countries have all reported NORM contamination. The purpose of this paper is to discuss some of the international regulations or guidelines that have been promulgated concerning NORM in the oil and gas industry. Additionally, the impact of these regulations or guidelines on non-oil and gas industries will also be discussed. A comparison of these regulations or guidelines to those generally found in the United States shall be drawn

The Jules Horowitz reactor, a new high performance European material testing reactor open to international users: present status and objectives

International Nuclear Information System (INIS)

Iracane, D.; Bignan, G.

2010-01-01

The development of nuclear power as a sustainable and competitive energy source will continue to require research and development of fuel and material behaviour under irradiation. This necessitates a high performance material testing reactor (MTR). Facing the obsolescence of most of the existing MTR in Europe, France decided a few years ago the construction of the RJH (Jules Horowitz reactor). RJH is designed, built and will be operated as an international user facility. A first set of experimental hosting devices is being designed. For instance, there are the in-core CALIPSO Nak integrated loop for material studies and other loops for fuel studies under nominal or off-normal or accidental conditions. The RJH international program will focus on the following subjects: -) fuel reliability, assessed through power ramps tests and post-irradiation examination; -) Loss of coolant tests done out-of-pile in a first phase and in-pile in a possible second phase; and -) source term tests addressing fission products release. The paper reports also the point of view of VATTENFALL (a Swedish power utility), as a potential European RJH user. (A.C.)

The Jules Horowitz Reactor - A new High Performance European Material Testing Reactor open to International Users Present Status and Objectives

International Nuclear Information System (INIS)

Iracane, Daniel; Bignan, Gilles; Lindbaeck, Jan-Erik; Blomgren, Jan

2010-01-01

The development of sustainable nuclear energy requires R and D on fuel and material behaviour under irradiation with a high level of performance in order to meet the needs and challenges for the benefit of industry, research and public bodies. These stakes require a sustainable and secured access to an up-to-date high performance Material Testing Reactor. Following a broad survey within the European Research Area, the international community agreed that the need for Material Test Reactors in support of nuclear power plant safety and operation will continue in the context of sustainable nuclear energy. The Jules Horowitz Reactor project (JHR) copes with this context. JHR is designed as a user facility addressing the needs of the international community. This means: - flexibility with irradiation loops able to reproduce a large variation in operation conditions of different power reactor technologies, - high flux capacity to address Generations II, III, and IV needs. JHR is designed, built and operated as an international user facility because: - Given the maturity and globalization of the industry, domestic tools have no more the required level of economic and technical efficiency. Meanwhile, countries with nuclear energy need an access to high performance irradiation experimental capabilities to support technical skill and guarantee the competitiveness and safety of nuclear energy. - Many research items related to safety or public policy (waste management, etc.) require international cooperation to share costs and benefits of resulting consensus. JHR design is optimised for offering high performance material and fuel irradiation capability for the coming decades. This project is driven and funded by an international consortium gathering vendors, utilities and public stakeholders. This consortium has been set up in March 2007 when the construction began. The construction is in progress and the start of operation is scheduled for 2014. The JHR is a research

Two new methods to determine the adhesion by means of internal friction in materials covered with films

International Nuclear Information System (INIS)

Colorado, H. A.; Ghilarducci, A. A.; Salva, H. R.

2006-01-01

Two new models are proposed to determine the adhesion energy be means of the internal friction technique (IF) in thin films layered materials. for the first method is necessary to determine enthalpy by means of the IF technique, for which the adhesion work has been determined with experimental data. In the second method are necessary to perform IF tests at constant temperature. (Author)

Energy demand for materials in an international context

NARCIS (Netherlands)

Worrell, Ernst; Carreon, Jesus Rosales

2017-01-01

Materials are everywhere and have determined society. The rapid increase in consumption of materials has led to an increase in the use of energy and release of greenhouse gas (GHG) emissions. Reducing emissions in material-producing industries is a key challenge. If all of industry switched to

Effect of plasma spraying modes on material properties of internal combustion engine cylinder liners

Science.gov (United States)

Timokhova, O. M.; Burmistrova, O. N.; Sirina, E. A.; Timokhov, R. S.

2018-03-01

The paper analyses different methods of remanufacturing worn-out machine parts in order to get the best performance characteristics. One of the most promising of them is a plasma spraying method. The mathematical models presented in the paper are intended to anticipate the results of plasma spraying, its effect on the properties of the material of internal combustion engine cylinder liners under repair. The experimental data and research results have been computer processed with Statistica 10.0 software package. The pare correlation coefficient values (R) and F-statistic criterion are given to confirm the statistical properties and adequacy of obtained regression equations.

IFMIF [International Fusion Materials Irradiation Facility], an accelerator-based neutron source for fusion components irradiation testing: Materials testing capabilities

International Nuclear Information System (INIS)

Mann, F.M.

1988-08-01

The International Fusion Materials Irradiation Facility (IFMIF) is proposed as an advanced accelerator-based neutron source for high-flux irradiation testing of large-sized fusion reactor components. The facility would require only small extensions to existing accelerator and target technology originally developed for the Fusion Materials Irradiation Test (FMIT) facility. At the extended facility, neutrons would be produced by a 0.1-A beam of 35-MeV deuterons incident upon a liquid lithium target. The volume available for high-flux (>10/sup 15/ n/cm/sup 2/-s) testing in IFMITF would be over a liter, a factor of about three larger than in the FMIT facility. This is because the effective beam current of 35-MeV deuterons on target can be increased by a factor of ten to 1A or more. Such an increase can be accomplished by funneling beams of deuterium ions from the radio-frequency quadruple into a linear accelerator and by taking advantage of recent developments in accelerator technology. Multiple beams and large total current allow great variety in available testing. For example, multiple simultaneous experiments, and great flexibility in tailoring spatial distributions of flux and spectra can be achieved. 5 refs., 2 figs., 1 tab

JPRS Report, Science & Technology, Europe, EC Commissioners Evaluate Electronics, Computer Industries

Science.gov (United States)

1991-06-14

American firms of foreign origin as regards R&TD is being practised by the Department of Defense, and Sematech is one example here. As negotiations... taxation measures. Training schemes for staff in the banking sector encom- passing both the financial side and computerized sys- tems applications

PREFACE: PASREG 2003: International Workshop on Processing and Applications of Superconducting (RE)BCO Large Grain Materials

Science.gov (United States)

Murakami, Masato; Cardwell, David; Salama, Kamel; Krabbes, Gernot; Habisreuther, Tobias; Gawalek, Wolfgang

2005-02-01

Superconducting melt-textured bulk (RE)BCO large grain materials are one of the most promising materials for power applications of high temperature superconductivity at the liquid nitrogen temperature range. Industrial applications are expected in high-speed low-loss magnetic bearings for flywheel energy storage devices, high-dynamic high-torque electric reluctance motors, and MAGLEV transportation systems. The material has high magnetic field trapping capability and therefore a new class of high-field superconducting permanent magnets will soon appear. However, there is still the need to improve the magnetic and mechanical material properties, as well as to increase the single domain size. This special issue contains papers concerning these topics presented at the International Workshop on the Processing and Applications of Superconducting (RE)BCO Large Grain Materials. The workshop was held on the 30 June-2 July 2003 in Jena, Germany, and was organized by the Institut fuer Physikalische Hochtechnologie, Jena. It was the fourth in the series of PASREG workshops after Cambridge, UK (1997), Morioka, Japan (1999), and Seattle, USA (2001). Sixty two contributions were presented at the workshop, 38 oral presentations and 24 poster presentations. This special issue contains 42 papers. The editors are grateful for the support of many colleagues who reviewed the manuscripts to guarantee their high technical quality. The editors also wish to thank Doris Litzkendorf and Tobias Habisreuther from Institut fuer Physikalische Hochtechnologie, Jena, for their assistance with the organization and handling of the manuscripts. Many thanks to the workshop co-chairman Gernot Krabbes from Leibniz-Institut fuer Festkoerper und Werkstoffforschung, Dresden, for hosting the workshop participants in Dresden. Finally, all attendees wish to acknowledge the efforts of Wolfgang Gawalek, Tobias Habisreuther, Doris Litzkendorf and the Team of Department Magnetics from the Institut fuer

Characterization of the materials used in the construction of a physical phantom for calibration of 18F-FDG internal dosimetry system

International Nuclear Information System (INIS)

Vital, Katia D.; Mendes, Bruno M.; Fonseca, Telma C.F.; Silva, Teógenes A. da

2017-01-01

The Internal Dosimetry Laboratory (LDI) of the Nuclear Technology Development Center (CDTN) in Minas Gerais, Brazil, is responsible for the routine monitoring of Occupationally Exposed Individuals (OEIs) to 18 F-FDG and other radiopharmaceuticals produced at CDTN. The monitoring system is usually calibrated using a physical head simulator, since 18 F is usually incorporated into the brain at the time of contamination. However, the geometry of the brain is not adequately represented by the latex pocket, which does not fill the entire volume of the volume skull. In this study, the characterization of the materials regarding the composition, density and attenuation coefficient of the materials used in the production of the new physical head simulator was carried out. An equivalent tissue material containing 97% water, 2.5% agar, 0.5% urea and 8 MBq of 18 F-FDG was produced, the interior of the skull was filled with the material. After solidification, experimental measurements were performed on the NaI(Tl) 3 x 3 s cintillation detector, the density of the simulant material was determined by the flotation method and the attenuation coefficient of the XCOM database software provided by NIST. It was concluded that the PVC skull has acceptable characteristics to simulate a human skull in 18 F-FDG internal dosimetry. The agar gel was shown to be a stable material capable of modeling different geometries and simulating the incorporation of 18 F-FDG into the brain. (author)

Magnetic fusion energy plasma interactive and high heat flux components. Volume III. Strategy for international collaborations in the areas of plasma materials interactions and high heat flux materials and components development

International Nuclear Information System (INIS)

Gauster, W.B.; Bauer, W.; Roberto, J.B.; Post, D.E.

1984-01-01

The purpose of this summary is to assess opportunities for such collaborations in the specific areas of Plasma Materials Interaction and High Heat Flux Materials and Components Development, and to aid in developing a strategy to take advantage of them. After some general discussion of international collaborations, we summarize key technical issues and the US programs to address them. Then follows a summary of present collaborations and potential opportunities in foreign laboratories

Automatic on-line detection system design research on internal defects of metal materials based on optical fiber F-P sensing technology

Science.gov (United States)

Xia, Liu; Shan, Ning; Chao, Ban; Caoshan, Wang

2016-10-01

Metal materials have been used in aerospace and other industrial fields widely because of its excellent characteristics, so its internal defects detection is very important. Ultrasound technology is used widely in the fields of nondestructive detection because of its excellent characteristic. But the conventional detection instrument for ultrasound, which has shortcomings such as low intelligent level and long development cycles, limits its development. In this paper, the theory of ultrasound detection is analyzed. A computational method of the defects distributional position is given. The non-contact type optical fiber F-P interference cavity structure is designed and the length of origin cavity is given. The real-time on-line ultrasound detecting experiment devices for internal defects of metal materials is established based on the optical fiber F-P sensing system. The virtual instrument of automation ultrasound detection internal defects is developed based on LabVIEW software and the experimental study is carried out. The results show that this system can be used in internal defect real-time on-line locating of engineering structures effectively. This system has higher measurement precision. Relative error is 6.7%. It can be met the requirement of engineering practice. The system is characterized by simple operation, easy realization. The software has a friendly interface, good expansibility, and high intelligent level.

International Round Table “Tatar Materials in Polish Archives” (Warsaw, 31st March – 1st April, 2016

Directory of Open Access Journals (Sweden)

M.M. Gibatdinov

2016-12-01

Full Text Available This article present a short report on the International round table “Tatar materials in Polish archives” organized in Warsaw on March 31 – April 1, 2016. Round table was a result of international scientific cooperation between Marjani Institute of History, Polish Academy of Sciences, University of Warsaw, Institute for Caucasian-, Tatar- and Turkestan Studies (ICATAT. It was a part of the long-term research project “Tatar Materials in Foreign Archives” carried out by the Marjani Institute of History in the framework of State Program of the Republic of Tatarstan “Preserving of Tatar Ethnical Identity (for years 2014–2016.” The following papers was presented on the round table: “On results of recent researches of Tatar materials in Polish archives” by Prof., Dr. Dariusz Kołodziejczyk, Director of the Institute of History, University of Warsaw; “The New Records of Old Heritage – Documents about Tatars from Regional and Private Archives in Polish-German Context”, by Dr. Mieste Hottop-Riecke, Director of ICATAT and Dr. Stephan Theilig, Director of Brandenburg-Preußen Museum Wustrau; “Maniere de Faire la Guerre des Tartares’ as Hybrid War in the Military Art of Crimean and Dobruja Tatars in the Early modern Time”, by Dr. Andrzej Gliwa, University of Warsaw, Department of History, Faculty Member; “Tatar Documents in Archives and Museums in Bialystok” by Dr. Artur Konopacki, Assistant Professor in Faculty of Pedagogy and Psychology, University of Bialystok; ”The first results of international research project ”Yazma Miras – Written Heritage” by Marat Gibatdinov. Participants of round table discussed a possible prospects for future cooperation in the field of researching and digitalizing of Tatar materials from Polish archives. During the conference the meetings with the representatives of Tatar community in Poland and Lithuania was organized, as well as the study visits to the Tatar Mosque and Tatar

FOREWORD: 12th International Workshop on Plasma-Facing Materials and Components for Fusion Applications 12th International Workshop on Plasma-Facing Materials and Components for Fusion Applications

Science.gov (United States)

Kreter, Arkadi; Linke, Jochen; Rubel, Marek

2009-12-01

The 12th International Workshop on Plasma-Facing Materials and Components for Fusion Applications (PFMC-12) was held in Forschungszentrum Jülich (FZJ) in Germany in May 2009. This symposium is the successor to the International Workshop on Carbon Materials for Fusion Applications series. Between 1985 and 2003, 10 'Carbon Workshops' were organized in Jülich, Stockholm and Hohenkammer. After this time, the scope of the symposium was redefined to reflect the new requirements of ITER and the ongoing evolution of the field. The workshop was first organized under its new name in 2006 in Greifswald, Germany. The main objective of this conference series is to provide a discussion forum for experts from research institutions and industry dealing with materials for plasma-facing components in present and future controlled fusion devices. The operation of ASDEX-Upgrade with tungsten-coated wall, the fast progress of the ITER-Like Wall Project at JET, the plans for the EAST tokamak to install tungsten, the start of ITER construction and a discussion about the wall material for DEMO all emphasize the importance of plasma-wall interactions and component behaviour, and give much momentum to the field. In this context, the properties and behaviour of beryllium, carbon and tungsten under plasma impact are research topics of foremost relevance and importance. Our community realizes both the enormous advantages and serious drawbacks of all the candidate materials. As a result, discussion is in progress as to whether to use carbon in ITER during the initial phase of operation or to abandon this element and use only metal components from the start. There is broad knowledge about carbon, both in terms of its excellent power-handling capabilities and the drawbacks related to chemical reactivity with fuel species and, as a consequence, about problems arising from fuel inventory and dust formation. We are learning continuously about beryllium and tungsten under fusion conditions, but our

International training course on implementation of state systems of accounting for and control of nuclear materials

International Nuclear Information System (INIS)

1982-12-01

The course was developed to provide practical training in the implementation and operation of a national system of nuclear materials accountability and control that satisfies both national and international safeguards requirements. Major emphasis for the 1982 course was placed on methods for safeguarding reactor facilities - both research reactors and power reactors plus their associated spent-fuel fuel storage. Separate abstracts have been prepared for 23 of the sessions; one of the remaining sessions had been previously abstracted

International Outsourcing and Productivity Growth

OpenAIRE

Martin Falk; Yvonne Wolfmayr

2008-01-01

This study investigates the impact of international outsourcing to low? and high income countries on total factor productivity growth based on manufacturing industry data for 14 OECD countries from 1995 ? 2000. We find that the broad measure of international outsourcing of material inputs to low income countries is significantly negatively related to productivity growth. Furthermore, while the narrow measure of international outsourcing of materials is not significant, purchased services from...

Program of assessment of mechanical and corrosion mechanical properties of reactor internals materials due to operation conditions in WWERs

International Nuclear Information System (INIS)

Ruscak, M.; Zamboch, M.

1998-01-01

Reactor internals are subject to three principle operation influences: neutron and gamma irradiation, mechanical stresses, both static and dynamic, and coolant chemistry. Several cases of damage have been reported in previous years in both boiling and pressure water reactors. They are linked with the term of irradiation assisted stress corrosion cracking as a possible damage mechanism. In WWERs, the principal material used for reactor internals is austenitic titanium stabilized stainless steel 08Kh18N10T, however high strength steels are used as well. To assess the changes of mechanical properties and to determine whether sensitivity to intergranular cracking can be increased by high neutron fluences, the experimental program has been started. The goal is to assure safe operation of the internals as well as life management for all planned operation period. The program consists of tests of material properties, both mechanical and corrosion-mechanical. Detailed neutron fluxes calculation as well as stress and deformation calculations are part of the assessment. Model of change will be proposed in order to plan inspections of the facility. In situ measurements of internals will be used to monitor exact status of structure during operation. Tensile specimens manufactured from both base metal and model weld joint have been irradiated to the total fluences of 3-20 dpa. Changes of mechanical properties are tested by the tensile test, stress corrosion cracking tests are performed in the autoclave with water loop and active loading. Operation temperature, pressure and water chemistry are chosen for the tests. (author)

Energy demand for materials in an international context.

Science.gov (United States)

Worrell, Ernst; Carreon, Jesus Rosales

2017-06-13

Materials are everywhere and have determined society. The rapid increase in consumption of materials has led to an increase in the use of energy and release of greenhouse gas (GHG) emissions. Reducing emissions in material-producing industries is a key challenge. If all of industry switched to current best practices, the energy-efficiency improvement potential would be between 20% and 35% for most sectors. While these are considerable potentials, especially for sectors that have historically paid a lot of attention to energy-efficiency improvement, realization of these potentials under current 'business as usual' conditions is slow due to a large variety of barriers and limited efforts by industry and governments around the world. Importantly, the potentials are not sufficient to achieve the deep reductions in carbon emissions that will be necessary to stay within the climate boundaries as agreed in the 2015 Paris Conference of Parties. Other opportunities need to be included in the menu of options to mitigate GHG emissions. It is essential to develop integrated policies combining energy efficiency, renewable energy and material efficiency and material demand reduction, offering the most economically attractive way to realize deep reductions in carbon emissions.This article is part of the themed issue 'Material demand reduction'. © 2017 The Author(s).

Contribution of materials investigations and operating experience of reactor vessel internals to PWRs' safety, performance and reliability

International Nuclear Information System (INIS)

Lemaire, E.; Monteil, N.; Jardin, N.; Doll, M.

2015-01-01

The Reactor Pressure Vessel Internals (RVI) include all the components inside the pressure vessel, except the nuclear fuel, the rod cluster assemblies and the instrumentation. The RVI consist of bolted and welded structures that are divided into two sub-assemblies: the upper internals which are removed at every refueling outage and the lower internals which are systematically removed for inspection at every 10-year outage. The main functions of the RVI are to position the core, to support it, and to provide a coolant flow by channeling the fluid. Moreover, the lower internals contribute to a neutron protection of the reactor pressure vessel by absorbing most of the neutron flux from the core. Depending on their location and material composition, the RVI components can face different ageing phenomena, that are actual or potential (such as wear, fatigue, stress corrosion cracking, irradiation assisted stress corrosion cracking, hardening and loss of ductility due to neutron irradiation, irradiation creep and irradiation swelling). EDF has developed a strategy for managing ageing and demonstrating the capacity of the RVI to perform their design functions over 40 years of operation. This overall approach is periodically revisited to take into account the most recent knowledge obtained from the following main topics: Safety Analyses, Research-Development programs, In-Service Inspection (ISI) results, Maintenance programs and Metallurgical Examinations. Based on continuous improvements in those fields, the goal of this paper is to present the way that materials investigations and operating experience obtained on RVI are managed by EDF to improve RVI safety, performance and reliability. It is shown that a perspective of 60 years of operation of RVI components is supported by large Research-Development efforts combined with field experience. (authors)

Selected Peer-Reviewed Articles from The International Meeting on Developments in Materials, Processes and Applications of Nanotechnology (MPA 2008), UK

NARCIS (Netherlands)

Ali, Nasar; De Hosson, Jeff. Th. M.; Ahmed, W.

The International Meeting on Developments in Materials, Processes and Applications of Nanotechnology (MPA 2008) held at Robinson College, University of Cambridge, UK was the second event of the MPA conference series. The first MPA-2007, held at the University of Ulster, UK officially launched the

3rd International Meeting for Researchers in Materials and Plasma Technology (IMRMPT) and 1st Symposium on Nanoscience and Nanotechnology

International Nuclear Information System (INIS)

2016-01-01

These proceedings present the written contributions of the participants of the 3rd International Meeting for Researchers in Materials and Plasma Technology (3rd IMRMPT) and the 1st Symposium on Nanoscience and Nanotechnology which was held from 4 to May 9, 2015 at the Dann Carlton Hotel Bucaramanga, Colombia, organized by the faculty of science of the Universidad Industrial de Santander (UIS) and the basic science department of the Universidad Pontificia Bolivariana. This was the third version of biennial meetings that began in 2011. The five-day scientific program of the 3rd IMRMPT consisted of 24 Magisterial Conferences, 70 Oral Presentations, 185 Poster Presentations, 3 Courses and 1 Discussion Panel with the participation of undergraduate and graduate students, professors, researchers and entrepreneurs from Colombia, Russia, Germany, France, Spain, England, United States, Mexico, Argentina, Uruguay, Brazil, Venezuela, among others. Moreover, the objective of IMRMPT was to bring together national and international researchers in order to establish a network of scientific cooperation with a global impact in the area of the science and the technology of materials; to promote the exchange of creative ideas and the effective transfer of scientific knowledge, from fundamental research to innovation applied to industrial solutions and to advances in the development of new research allowing to increase the lifetime of the materials used in the industry by means of efficient transference of the knowledge between sectors academia and industry. The topics covered in the 3rd IMRMPT include New Materials, Surface Physics, Structural Integrity, Renewable Energy, Online Process Control, Non Destructive Evaluation, Characterization of Materials, Laser and Hybrid Processes, Thin Films and Nanomaterials, Surface Hardening Processes, Wear and Corrosion/Oxidation, Plasma Applications and Technologies, Modelling, Simulation and Diagnostics, Biomedical Coatings, Surface Treatments

12th Russia/CIS/Baltic/Japan Symposium on Ferroelectricity and 9th International Conference on Functional Materials and Nanotechnologies (RCBJSF–2014–FM and NT)

International Nuclear Information System (INIS)

Sternberg, Andris; Grinberga, Liga; Sarakovskis, Anatolijs; Rutkis, Martins

2015-01-01

The joint International Symposium RCBJSF–2014–FM and NT successfully has united two international events – 12th Russia/CIS/Baltic/Japan Symposium on Ferroelectricity (RCBJSF-12) and 9th International Conference Functional Materials and Nanotechnologies (FM and NT-2014). The RCBJSF symposium is a continuation of series of meetings on ferroelectricity, the first of which took place in Novosibirsk (USSR) in 1976. FM and NT conferences started in 2006 and have been organized by Institute of Solid State Physics, University of Latvia in Riga. In 2012 the International program committee decided to transform this conference into a traveling Baltic State conference and the FM and NT-2013 was organized by the Institute of Physics, University of Tartu, Estonia. In 2014 the joint international symposium RCBJSF–2014–FM and NT was organized by the Institute of Solid State Physics, University of Latvia and was part of Riga – 2014, the European Capital of Culture event. The purpose of the joint Symposium was to bring together scientists, students and high-level experts in solid state physics, materials science, engineering and related disciplines. The number of the registered participants from 26 countries was over 350. During the Symposium 128 high quality scientific talks (5 plenary, 42 invited, 81 oral) and over 215 posters were presented. All presentations were divided into 4 parallel sessions according to 4 main topics of the Symposium: Ferroelectricity, including ferroelectrics and multiferroics, pyroelectrics, piezoelectrics and actuators, integrated ferroelectrics, relaxors, phase transitions and critical phenomena. Multifunctional Materials, including theory, multiscale and multiphenomenal material modeling and simulation, advanced inorganic, organic and hybrid materials. Nanotechnologies, including progressive methods, technologies and design for production, investigation of nano- particles, composites, structures, thin films and coatings. Energy, including

Characterization of the materials used in the construction of a physical phantom for calibration of {sup 18}F-FDG internal dosimetry system

Energy Technology Data Exchange (ETDEWEB)

Vital, Katia D.; Mendes, Bruno M.; Fonseca, Telma C.F.; Silva, Teógenes A. da, E-mail: katiadvitall@gmail.com [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte - MG (Brazil)

2017-07-01

The Internal Dosimetry Laboratory (LDI) of the Nuclear Technology Development Center (CDTN) in Minas Gerais, Brazil, is responsible for the routine monitoring of Occupationally Exposed Individuals (OEIs) to {sup 18}F-FDG and other radiopharmaceuticals produced at CDTN. The monitoring system is usually calibrated using a physical head simulator, since {sup 18}F is usually incorporated into the brain at the time of contamination. However, the geometry of the brain is not adequately represented by the latex pocket, which does not fill the entire volume of the volume skull. In this study, the characterization of the materials regarding the composition, density and attenuation coefficient of the materials used in the production of the new physical head simulator was carried out. An equivalent tissue material containing 97% water, 2.5% agar, 0.5% urea and 8 MBq of {sup 18}F-FDG was produced, the interior of the skull was filled with the material. After solidification, experimental measurements were performed on the NaI(Tl) 3 {sup x}3{sup s}cintillation detector, the density of the simulant material was determined by the flotation method and the attenuation coefficient of the XCOM database software provided by NIST. It was concluded that the PVC skull has acceptable characteristics to simulate a human skull in {sup 18}F-FDG internal dosimetry. The agar gel was shown to be a stable material capable of modeling different geometries and simulating the incorporation of {sup 18}F-FDG into the brain. (author)

Historical cartographic materials as a source for international and cadastral boundary management in rivers

Science.gov (United States)

Srebro, Haim

2018-05-01

International and cadastral boundaries are important for ensuring stable legal territorial matters. This article deals with the long-term location and management of boundaries in rivers and the depiction of the rivers on cartographic materials. A few countries have agreed that the boundary will not follow changes in the river (like in the Mongolia-China Border Treaty), whereas most agree that the boundary will follow slow, natural and gradual changes in the river (like is stated in the Israel-Jordan Peace Treaty). The international boundary under the British Mandate between Palestine and Trans-Jordan in the Jordan and Yarmuk rivers was defined in 1922. The cadastral boundaries were defined in these rivers in the 1930s along the international boundary. For more than 70 years, until the Israel-Jordan 1994 Peace Treaty, the rivers have changed their channels east and westward to distances up to hundreds of meters. During that period the mandatory boundaries in these rivers changed their political status to the armistice lines, the cease-fire lines, and to international boundaries between sovereign states. These lines were usually delineated on topographic maps in the rivers, drawn by cartographers following contemporary map revision. During that entire period the cadastral boundaries were not changed in order to adapt them to the actual position of the rivers and to the delineated international boundaries. Owing to large water works on both rivers, including the construction of dams and diversion channels in order to meet the increasing needs of the population on both sides, the water flow of the rivers decreased dramatically to less than one tenth of the original natural flow. The population today is more than ten times than it used to be under the British Mandate. The changes in the water channels during the last 20 years since the 1994 peace treaty are in the magnitude of 10 meters versus hundreds of meters in the past. In addition, intensive land cultivation

Scintilla: A New International Platform for the Development, Evaluation and Benchmarking of Technologies to Detect Radioactive and Nuclear Material

International Nuclear Information System (INIS)

Sannie, G.; Normand, S.; Peerani, P.; Tagziria, H.; Friedrich, H.; Chmel, S.; De Vita, R.; Pavan, M.; Grattarola, M.; Botta, E.; Kovacs, A.S.; Lakosi, L.; Baumhauer, C.; Equios, M.; Petrossian, G.; Picard, J.M.; Dermody, G.; Crossingham, G.

2013-06-01

For Homeland Security, enhanced detection and identification of radioactive sources and nuclear material has become of increasing importance. The scintilla project aims at minimizing the risk of radioactive sources dissemination especially with masked and shielded material. SCINTILLA offers the capacity to finding a reliable alternative to Helium-3 based detection systems since the gas which is predominantly used in nuclear safeguards and security applications has now become very expensive, rare and nearly unavailable. SCINTILLA benchmarks will be based on international standards. Radiation Portal testing being carried out at the Joint Research Centre (JRC) in Ispra (Italy). (authors)

20th International Training Course (ITC-20) on the physical protection of nuclear facilities and materials evaluation report.

Energy Technology Data Exchange (ETDEWEB)

Ramirez, Amanda Ann

2008-09-01

The goal of this evaluation report is to provide the information necessary to improve the effectiveness of the ITC provided to the International Atomic Energy Agency Member States. This report examines ITC-20 training content, delivery methods, scheduling, and logistics. Ultimately, this report evaluates whether the course provides the knowledge and skills necessary to meet the participants needs in the protection of nuclear materials and facilities.

International target values 2000 for measurement uncertainties in safeguarding nuclear materials

International Nuclear Information System (INIS)

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

2001-01-01

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

Seismic risk analysis for the Atomics International Nuclear Materials Development Facility, Santa Susana California

International Nuclear Information System (INIS)

1978-01-01

This report presents the results of a detailed seismic risk analysis of the Nuclear Materials Development Facility (NMDF) operated by Atomics International at Santa Susana, California. The historical seismic record was established after a review of available literature, consultation with operators of local seismic arrays and examination of appropriate seismic data bases including the USGS, California Institute of Technology and NEIS data bases. The resulting seismic record, covering the period 1969 to 1977, was used to identify all possible sources of seismicity that could affect the site. The best estimate curve indicates that the facility will experience 30% g with a return period of 55 years and 60% g with a return period of 750 years

Seismic risk analysis for the Atomics International Nuclear Materials Development Facility, Santa Susana California

Energy Technology Data Exchange (ETDEWEB)

1978-12-29

This report presents the results of a detailed seismic risk analysis of the Nuclear Materials Development Facility (NMDF) operated by Atomics International at Santa Susana, California. The historical seismic record was established after a review of available literature, consultation with operators of local seismic arrays and examination of appropriate seismic data bases including the USGS, California Institute of Technology and NEIS data bases. The resulting seismic record, covering the period 1969 to 1977, was used to identify all possible sources of seismicity that could affect the site. The best estimate curve indicates that the facility will experience 30% g with a return period of 55 years and 60% g with a return period of 750 years.

76 FR 70758 - Notice Pursuant to the National Cooperative Research and Production Act of 1993-Sematech, Inc. D...

Science.gov (United States)

2011-11-15

..., test, make, market, or support materials, equipment, processes, software, systems, or facilities for... enhancing semiconductor manufacturing equipment productivity, contributing to increased automation in the...

Procedures for the accounting and control of nuclear materials in large research centres, as related to the needs of international safeguards

International Nuclear Information System (INIS)

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

1976-07-01

In signatory states of the Non-Proliferation Treaty nuclear material is subject to the supervision of the International Atomic Energy Agency. The IAEA safeguards concept intended for nuclear material has, so far, been predominantly applied to nuclear facilities of the nuclear fuel cycle. It is the aim of this report to consider the applicability of these control measures to a nuclear research centre. The report refers to the concrete example of the Juelich Nuclear Research Centre (KFA). The particular features of a nuclear research centre and the handling of nuclear material in the KFA are described. A review is given of the various licence areas and permitted handling quantities as well as of the inventories and flow of nuclear material. The concept of a control system for a nuclear research centre satisfying the operator's requirements, national requirement and international obligations at the same time is developed along these lines. The essential characteristic of the concept is a far-reaching clarity of the distribution of nuclear material items within the Nuclear Research Centre. The clarity desired will be achieved by means of an integrated accountancy system processing all necessary data with the aid of a central computer and remote terminals. The availability of information is based on differentiated material acountancy in conjunction with adequate measurement of nuclear material data. In the case of the KFA two groups are formed by research reactors and critical assemblies. Research institutes and central departments the permitted handling quantities of which do not exceed 5 eff.kg constitute a further group. Two further groups are formed for cases where the permitted handling quantities are above or below 1 eff.kg. The report shows the safeguards measures that can be applied in certain circumstances and conditions in a nuclear research centre

IAEA safeguards and classified materials

International Nuclear Information System (INIS)

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

1997-01-01

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

Novel artificial stool material for external quality assurance (EQA) on a fecal immunochemical test for hemoglobin (FIT): The confirmed utility of stable hemoglobin and an internal standard material.

Science.gov (United States)

Yasui, Ryota; Yamada, Miyu; Takehara, Shizuka; Sakurabayashi, Ikunosuke; Watanabe, Katsunori

2018-04-16

The fecal immunochemical test for hemoglobin (FIT), which detects lower gastrointestinal bleeding, is widely accepted for population-based colorectal cancer (CRC) screening programs. However, the FIT screening process has not been standardized yet, and standardizing the pre-analytical phase and establishing an external quality assurance (EQA) program compliant with ISO requirements is urgently needed. Although there have been various attempts to establish EQA materials suitable for FIT, no materials have yet been reported to have sufficient uniformity and acceptable immunochemical stability of hemoglobin (Hb). The Health Care Technology Foundation (HECTEF; Tokyo Japan) is now developing a ready-to-use artificial stool containing Hb and an internal standard, glycerol. Accordingly, we verified the adaptability and efficacy of this material for the evaluation of the specimen collection phase of FIT. This material uniformly contained both Hb and glycerol. The glycerol allowed us to estimate the weight of the collected artificial stool and to correct the Hb concentration with the estimated weight. Furthermore, the stability of both Hb and glycerol were confirmed to be sufficient for an EQA material under appropriate storage, in-use, repeated freeze-thaw, and heated conditions. These in-house performance characteristics suggest that HECTEF artificial stool is acceptable as an EQA material for FIT. Copyright © 2018 Elsevier B.V. All rights reserved.

International law

CERN Document Server

Shaw, Malcolm N

2017-01-01

International Law is the definitive and authoritative text on the subject, offering Shaw's unbeatable combination of clarity of expression and academic rigour and ensuring both understanding and critical analysis in an engaging and authoritative style. Encompassing the leading principles, practice and cases, and retaining and developing the detailed references which encourage and assist the reader in further study, this new edition motivates and challenges students and professionals while remaining accessible and engaging. Fully updated to reflect recent case law and treaty developments, this edition contains an expanded treatment of the relationship between international and domestic law, the principles of international humanitarian law, and international criminal law alongside additional material on international economic law.

Studying international fuel cycle robustness with the GENIUSv2 discrete facilities/materials fuel cycle systems analysis tool

Energy Technology Data Exchange (ETDEWEB)

Wilson, P.H. [Dept. of Engineering Physics, University of Wisconsin-Madison (United States)

2009-06-15

GENIUSv2 (Global Evaluation of Nuclear Infrastructure Utilization Scenarios, hereafter 'GENIUS') is a discrete-facilities/materials nuclear fuel cycle systems analysis tool currently under development at the University of Wisconsin-Madison. For a given scenario, it models nuclear fuel cycle facilities (reactors, fuel fabrication, enrichment, etc.), the institutions that own them (utilities and governments), and the regions in which those institutions operate (sub-national, national, and super-national entities). Facilities work together to provide each other with the materials they need. The results of each simulation include the electricity production in each region as well as operational histories of each facility and isotopic and facility histories of each material object. GENIUS users specify an initial condition and a facility deployment plan. The former describes each region and institution in the scenario as well as facilities that exist at the start. The latter specifies all the facilities that will be built over the course of the simulation (and by which institutions). Each region, institution, and facility can be assigned financial parameters such as tax and interest rates, and facilities also get assigned technical information about how they actually operate. Much of the power of the data model comes from the flexibility to model individual entities to a fine level of detail or to allow them to inherit region-, institution-, or facility-type-specific default parameters. Most importantly to the evaluation of regional, national, and international policies, users can also specify rules that define the affinity (or lack thereof) for trade of particular commodities between particular entities. For instance, these rules could dictate that a particular region or institution always buy a certain commodity (ore, enriched UF{sub 6}, fabricated fuel, etc.) from a particular region or institution, never buy from that region, or merely have a certain

PREFACE: International Seminar on Science and Technology of Glass Materials (ISSTGM-2009)

Science.gov (United States)

Veeraiah, N.

2009-07-01

The progress of the human race is linked with the development of new materials and also the values they acquired in the course of time. Though the art of glass forming has been known from Egyptian civilization, the understanding and use of these glasses for technological applications only became possible once the structural aspects were revealed by the inspiring theories proposed by William H Zachariasen. Glass and glass ceramics have become the essential materials for modern technology. The applications of these materials are wide and cover areas such as optical communication, laser host, innovative architecture, bio-medical, automobile and space technology. As we master the technology, we must also learn to use it judiciously and for the overall development of all in this global village. The International Seminar on Science and Technology of Glass Materials (ISSTGM-2009) is organized to bring together scientists, academia and industry in order to discuss various aspects of the technology and to inspire young scholars to take up fruitful research. Various topics such as glass formation and glass-ceramics, glass structure, applications of glass and glass ceramics in nuclear waste management, radiation dosimetry, electronics and information technology, biotechnological applications, bulk metallic glasses, glasses containing nano-particles, hybrid glasses, novel glasses and applications in photonics, Non-linear optics and energy generation were discussed. In this volume, 59 research articles covering 18 invited talks, 10 oral presentations and 31 poster presentations are included. We hope these will serve as a valuable resource to all the scientists and scholars working with glass materials. Acharya Nagarjuna University, established in 1976, is named after the great Buddhist preceptor and philosopher, Acharya Nagarjuna, who founded a university on the banks of river Krishna some centuries ago. The University is situated between Vijayawada and Guntur, the famous

Radioactive material packaging performance testing

International Nuclear Information System (INIS)

Romano, T.

1992-06-01

In an effort to provide uniform packaging of hazardous material on an international level, recommendations for the transport of dangerous goods have been developed by the United Nations. These recommendations are performance oriented and contrast with a large number of packaging specifications in the US Department of Transportation's hazard materials regulations. This dual system presents problems when international shipments enter the US Department of Transportation's system. Faced with the question of continuing a dual system or aligning with the international system, the Research and Special Programs Administration of the US Department of Transportation responded with Docket HM-181. This began the transition toward the international transportation system. Following close behind is Docket HM-169A, which addressed low specific activity radioactive material packaging. This paper will discuss the differences between performance-oriented and specification packaging, the transition toward performance-oriented packaging by the US Department of Transportation, and performance-oriented testing of radioactive material packaging by Westinghouse Hanford Company. Dockets HM-181 and HM-169A will be discussed along with Type A (low activity) and Type B (high activity) radioactive material packaging evaluations

Using internally cooled cutting tools in the machining of difficult-to-cut materials based on Waspaloy

Directory of Open Access Journals (Sweden)

Yahya Isik

2016-05-01

Full Text Available Nickel-based superalloys such as Waspaloy are used for engine components and in the nuclear industry, where considerable strength and corrosion resistance at high operating temperatures are called for. These characteristics of such alloys cause increases in cutting temperature and resultant tool damage, even at low cutting speeds and low feed rates. Thus, they are classified as difficult-to-cut materials. This article presents a cooling method to be used in metal cutting based on a tool holder with a closed internal cooling system with cooling fluid circulating inside. Hence, a green cooling method that does not harm the environment and is efficient in removing heat from the cutting zone was developed. A series of cutting experiments were conducted to investigate the practicality and effectiveness of the internally cooled tool model. The developed system achieved up to 13% better surface quality than with dry machining, and tool life was extended by 12%. The results clearly showed that with the reduced cutting temperature of the internal cooling, it was possible to control the temperature and thus prevent reaching the critical cutting temperature during the turning process, which is vitally important in extending tool life during the processing of Waspaloy.

Methodology for Evaluating Raw Material Changes to RSRM Elastomeric Insulation Materials

Science.gov (United States)

Mildenhall, Scott D.; McCool, Alex (Technical Monitor)

2001-01-01

The Reusable Solid Rocket Motor (RSRM) uses asbestos and silicon dioxide filled acrylonitrile butadiene rubber (AS-NBR) as the primary internal insulation to protect the case from heat. During the course of the RSRM Program, several changes have been made to the raw materials and processing of the AS-NBR elastomeric insulation material. These changes have been primarily caused by raw materials becoming obsolete. In addition, some process changes have been implemented that were deemed necessary to improve the quality and consistency of the AS-NBR insulation material. Each change has been evaluated using unique test efforts customized to determine the potential impacts of the specific raw material or process change. Following the evaluations, the various raw material and process changes were successfully implemented with no detectable effect on the performance of the AS-NBR insulation. This paper will discuss some of the raw material and process changes evaluated, the methodology used in designing the unique test plans, and the general evaluation results. A summary of the change history of RSRM AS-NBR internal insulation is also presented.

Speaking in Tongues: Can International Graduate Students Read International Graduate Admissions Materials?

Science.gov (United States)

Taylor, Zachary W.

2017-01-01

A recent Educational Testing Services report (2016) found that international graduate students with a TOEFL score of 80--the minimum average TOEFL score for graduate admission in the United States--usually possess reading subscores of 20, equating to a 12th-grade reading comprehension level. However, one public flagship university's international…

Communication received from the permanent mission of Austria regarding the provision of certain additional information on production, inventories and international transfers of nuclear material and on exports of certain relevant equipment and non-nuclear material

International Nuclear Information System (INIS)

1996-01-01

The Director General received a note verbale of 13 June 1996 from Permanent Mission of Austria regarding the provision of certain additional information on production, inventories and international transfers of nuclear material and on exports of certain relevant equipment and non-nuclear material. In the light of the request expressed at the end of the note verbale, the text of the note verbale is being circulated

Communication received from the permanent mission of Finland regarding the provision of certain additional information on production, inventories and international transfers of nuclear material and on exports of certain relevant equipment and non-nuclear material

International Nuclear Information System (INIS)

1996-01-01

The Director General received a note verbale of 8 February 1996 from Permanent Mission of Finland regarding the provision of certain additional information on production, inventories and international transfers of nuclear material and on exports of certain relevant equipment and non-nuclear material. In the light of the request expressed at the and of the note verbale, the text of the note verbale is being circulated

Materials on the International Space Station - Forward Technology Solar Cell Experiment

Science.gov (United States)

Walters, R. J.; Garner, J. C.; Lam, S. N.; Vazquez, J. A.; Braun, W. R.; Ruth, R. E.; Lorentzen, J. R.; Bruninga, R.; Jenkins, P. P.; Flatico, J. M.

2005-01-01

This paper describes a space solar cell experiment currently being built by the Naval Research Laboratory (NRL) in collaboration with NASA Glenn Research Center (GRC), and the US Naval Academy (USNA). The experiment has been named the Forward Technology Solar Cell Experiment (FTSCE), and the purpose is to rapidly put current and future generation space solar cells on orbit and provide validation data for these technologies. The FTSCE is being fielded in response to recent on-orbit and ground test anomalies associated with space solar arrays that have raised concern over the survivability of new solar technologies in the space environment and the validity of present ground test protocols. The FTSCE is being built as part of the Fifth Materials on the International Space Station (MISSE) Experiment (MISSE-5), which is a NASA program to characterize the performance of new prospective spacecraft materials when subjected to the synergistic effects of the space environment. Telemetry, command, control, and communication (TNC) for the FTSCE will be achieved through the Amateur Satellite Service using the PCSat2 system, which is an Amateur Radio system designed and built by the USNA. In addition to providing an off-the-shelf solution for FTSCE TNC, PCSat2 will provide a communications node for the Amateur Radio satellite system. The FTSCE and PCSat2 will be housed within the passive experiment container (PEC), which is an approximately 2ft x2ft x 4in metal container built by NASA Langley Research Center (NASA LaRC) as part of the MISSE-5 program. NASA LaRC has also supplied a thin film materials experiment that will fly on the exterior of the thermal blanket covering the PCSat2. The PEC is planned to be transported to the ISS on a Shuttle flight. The PEC will be mounted on the exterior of the ISS by an astronaut during an extravehicular activity (EVA). After nominally one year, the PEC will be retrieved and returned to Earth. At the time of writing this paper, the

Internal exposure from building materials exhaling (222)Rn and (220)Rn as compared to external exposure due to their natural radioactivity content.

Science.gov (United States)

Ujić, Predrag; Celiković, Igor; Kandić, Aleksandar; Vukanac, Ivana; Durasević, Mirjana; Dragosavac, Dusan; Zunić, Zora S

2010-01-01

The main scope of this paper is to point out the importance of introducing radon and thoron exhalation measurements from building materials in the regulating frame. Currently (2009), such a regulation of this kind of exposure is not explicitly included in the Serbian regulating network. To this end, this work reports concentration measurements of (226)Ra, (232)Th and (40)K and radon and thoron exhalation rates from building materials used in Serbia. Following detailed analysis, it was noticed that both internal exposures to radon and/or thoron exhaling from building materials may exceed external exposures to their precursors contained therein.

Evaluation of internet-based patient education materials from internal medicine subspecialty organizations: will patients understand them?

Science.gov (United States)

Hansberry, David R; Agarwal, Nitin; John, Elizabeth S; John, Ann M; Agarwal, Prateek; Reynolds, James C; Baker, Stephen R

2017-06-01

The majority of Americans use the Internet daily, if not more often, and many search online for health information to better understand a diagnosis they have been given or to research treatment options. The average American reads at an eighth-grade level. The purpose of this study is to evaluate the readability of online patient education materials on the websites of 14 professional organizations representing the major internal medicine subspecialties. We used ten well-established quantitative readability scales to assess written text from patient education materials published on the websites of the major professional organizations representing the following subspecialty groups: allergy and immunology, cardiology, endocrinology, gastroenterology, geriatrics, hematology, hospice and palliative care, infectious disease, nephrology, oncology, pulmonology and critical care, rheumatology, sleep medicine, and sports medicine. Collectively the 540 articles analyzed were written at an 11th-grade level (SD 1.4 grade levels). The sleep medicine and nephrology websites had the most readable materials, written at an academic grade level of 8.5 ± 1.5 and 9.0 ± 0.2, respectively. Material at the infectious disease site was written at the most difficult level, with average readability corresponding to grades 13.9 ± 0.3. None of the patient education materials we reviewed conformed to the American Medical Association (AMA) and the National Institutes of Health (NIH) guidelines requiring that patient education articles be written at a third- to seventh-grade reading level. If these online resources were rewritten, it is likely that more patients would derive benefit from reading them.

Internal variables in thermoelasticity

CERN Document Server

Berezovski, Arkadi

2017-01-01

This book describes an effective method for modeling advanced materials like polymers, composite materials and biomaterials, which are, as a rule, inhomogeneous. The thermoelastic theory with internal variables presented here provides a general framework for predicting a material’s reaction to external loading. The basic physical principles provide the primary theoretical information, including the evolution equations of the internal variables. The cornerstones of this framework are the material representation of continuum mechanics, a weak nonlocality, a non-zero extra entropy flux, and a consecutive employment of the dissipation inequality. Examples of thermoelastic phenomena are provided, accompanied by detailed procedures demonstrating how to simulate them.

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.)

Ceramic breeder materials

International Nuclear Information System (INIS)

Johnson, C.E.

1990-01-01

The breeding blanket is a key component of the fusion reactor because it directly involves tritium breeding and energy extraction, both of which are critical to development of fusion power. The lithium ceramics continue to show promise as candidate breeder materials. This promise was recognized by the International Thermonuclear Reactor (ITER) design team in its selection of ceramics as the first option for the ITER breeder material. Blanket design studies have indicated properties in the candidate materials data base that need further investigation. Current studies are focusing on tritium release behavior at high burnup, changes in thermophysical properties with burnup, compatibility between the ceramic breeder and beryllium multiplier, and phase changes with burnup. Laboratory and in-reactor tests, some as part of an international collaboration for development of ceramic breeder materials, are underway. 32 refs., 1 fig., 1 tab

Metallic materials for heat exchanger components and highly stressed internal of HTR reactors for nuclear process heat generation

International Nuclear Information System (INIS)

1982-01-01

The programme was aimed at the development and improvement of materials for the high-temperature heat exchanger components of a process steam HTR. The materials must have high resistance to corrosion, i.e. carburisation and internal oxidation, and high long-term toughness over a wide range of temperatures. They must also meet the requirements set in the nuclear licensing procedure, i.e. resistance to cyclic stress and irradiation, non-destructive testing, etc. Initially, it was only intended to improve and qualify commercial alloys. Later on an alloy development programme was initiated in which new, non-commercial alloys were produced and modified for use in a nuclear process heat facility. Separate abstracts were prepared for 19 pays of this volume. (orig./IHOE) [de

Development of internal dose assessment procedure for workers in industries using raw materials containing naturally occurring radioactive materials

International Nuclear Information System (INIS)

Choi, Cheol Kyu; KIm, Yong Geon; Ji, Seung Woo; Kim, Kwang Pyo; Koo, Bon Cheol; Chang, Byung Uck

2016-01-01

It is necessary to assess radiation dose to workers due to inhalation of airborne particulates containing naturally occurring radioactive materials (NORM) to ensure radiological safety required by the Natural Radiation Safety Management Act. The objective of this study is to develop an internal dose assessment procedure for workers at industries using raw materials containing natural radionuclides. The dose assessment procedure was developed based on harmonization, accuracy, and proportionality. The procedure includes determination of dose assessment necessity, preliminary dose estimation, airborne particulate sampling and characterization, and detailed assessment of radiation dose. The developed dose assessment procedure is as follows. Radioactivity concentration criteria to determine dose assessment necessity are 10 Bq·g-1 for 40K and 1 Bq·g-1 for the other natural radionuclides. The preliminary dose estimation is performed using annual limit on intake (ALI). The estimated doses are classified into 3 groups (<0.1 mSv, 0.1-0.3 mSv, and >0.3 mSv). Air sampling methods are determined based on the dose estimates. Detailed dose assessment is performed using air sampling and particulate characterization. The final dose results are classified into 4 different levels (<0.1 mSv, 0.1-0.3 mSv, 0.3-1 mSv, and >1 mSv). Proper radiation protection measures are suggested according to the dose level. The developed dose assessment procedure was applied for NORM industries in Korea, including coal combustion, phosphate processing, and monazite handing facilities. The developed procedure provides consistent dose assessment results and contributes to the establishment of optimization of radiological protection in NORM industries

Development of internal dose assessment procedure for workers in industries using raw materials containing naturally occurring radioactive materials

Energy Technology Data Exchange (ETDEWEB)

Choi, Cheol Kyu; KIm, Yong Geon; Ji, Seung Woo; Kim, Kwang Pyo [College of Engineering, Kyung Hee University, Yongin (Korea, Republic of); Koo, Bon Cheol; Chang, Byung Uck [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2016-09-15

It is necessary to assess radiation dose to workers due to inhalation of airborne particulates containing naturally occurring radioactive materials (NORM) to ensure radiological safety required by the Natural Radiation Safety Management Act. The objective of this study is to develop an internal dose assessment procedure for workers at industries using raw materials containing natural radionuclides. The dose assessment procedure was developed based on harmonization, accuracy, and proportionality. The procedure includes determination of dose assessment necessity, preliminary dose estimation, airborne particulate sampling and characterization, and detailed assessment of radiation dose. The developed dose assessment procedure is as follows. Radioactivity concentration criteria to determine dose assessment necessity are 10 Bq·g-1 for 40K and 1 Bq·g-1 for the other natural radionuclides. The preliminary dose estimation is performed using annual limit on intake (ALI). The estimated doses are classified into 3 groups (<0.1 mSv, 0.1-0.3 mSv, and >0.3 mSv). Air sampling methods are determined based on the dose estimates. Detailed dose assessment is performed using air sampling and particulate characterization. The final dose results are classified into 4 different levels (<0.1 mSv, 0.1-0.3 mSv, 0.3-1 mSv, and >1 mSv). Proper radiation protection measures are suggested according to the dose level. The developed dose assessment procedure was applied for NORM industries in Korea, including coal combustion, phosphate processing, and monazite handing facilities. The developed procedure provides consistent dose assessment results and contributes to the establishment of optimization of radiological protection in NORM industries.

10th meeting of the International Conference on Protection of Materials and Structures from Space Environment

CERN Document Server

Tagawa, Masahito; Kimoto, Yugo; Protection of Materials and Structures From the Space Environment

2013-01-01

The goals of the 10th International Space Conference on “Protection of Materials and Structures from Space Environment” ICPMSE-10J, since its inception in 1992, have been to facilitate exchanges between members of the various engineering and science disciplines involved in the development of space materials, including aspects of LEO, GEO and Deep Space environments, ground-based qualification, and in-flight experiments and lessons learned from operational vehicles that are closely interrelated to disciplines of the atmospheric sciences, solar-terrestrial interactions and space life sciences. The knowledge of environmental conditions on and around the Moon, Mars, Venus and the low Earth orbit as well as other possible candidates for landing such as asteroids have become an important issue, and protecting both hardware and human life from the effects of space environments has taken on a new meaning in light of the increased interest in space travel and colonization of other planets.  And while many materia...

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)

Aims and methods of nuclear materials management

International Nuclear Information System (INIS)

Leven, D.; Schier, H.

1979-05-01

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

IFMIF, International Fusion Materials Irradiation Facility conceptual design activity cost report

International Nuclear Information System (INIS)

Rennich, M.J.

1996-12-01

This report documents the cost estimate for the International Fusion Materials Irradiation Facility (IFMIF) at the completion of the Conceptual Design Activity (CDA). The estimate corresponds to the design documented in the Final IFMIF CDA Report. In order to effectively involve all the collaborating parties in the development of the estimate, a preparatory meeting was held at Oak Ridge National Laboratory in March 1996 to jointly establish guidelines to insure that the estimate was uniformly prepared while still permitting each country to use customary costing techniques. These guidelines are described in Section 4. A preliminary cost estimate was issued in July 1996 based on the results of the Second Design Integration Meeting, May 20--27, 1996 at JAERI, Tokai, Japan. This document served as the basis for the final costing and review efforts culminating in a final review during the Third IFMIF Design Integration Meeting, October 14--25, 1996, ENEA, Frascati, Italy. The present estimate is a baseline cost estimate which does not apply to a specific site. A revised cost estimate will be prepared following the assignment of both the site and all the facility responsibilities

Preliminary results of the International Fusion Materials Irradiation Facility deuteron injector

Energy Technology Data Exchange (ETDEWEB)

Gobin, R.; Adroit, G.; Bogard, D.; Bourdelle, G.; Chauvin, N.; Delferriere, O.; Gauthier, Y.; Girardot, P.; Guiho, P.; Harrault, F.; Jannin, J. L.; Loiseau, D.; Mattei, P.; Roger, A.; Sauce, Y.; Senee, F.; Vacher, T. [Commissariat a l' Energie Atomique et aux Energie Alternatives, CEA/Saclay, DSM/IRFU, 91191-Gif/Yvette (France)

2012-02-15

In the framework of the IFMIF-EVEDA project (International Fusion Materials Irradiation Facility-Engineering Validation and Engineering Design Activities), CEA/IRFU is in charge of the design, construction, and characterization of the 140 mA continuous deuteron injector, including the source and the low energy beam line. The electron cyclotron resonance ion source which operates at 2.45 GHz is associated with a 4-electrode extraction system in order to minimize beam divergence at the source exit. Krypton gas injection is foreseen in the 2-solenoid low energy beam line. Such Kr injection will allow reaching a high level of space charge compensation in order to improve the beam matching at the radio frequency quadrupole (RFQ) entrance. The injector construction is now completed on the Saclay site and the first plasma and beam production has been produced in May 2011. This installation will be tested with proton and deuteron beams either in pulsed or continuous mode at Saclay before shipping to Japan. In this paper, after a brief description of the installation, the preliminary results obtained with hydrogen gas injection into the plasma chamber will be reported.

Current Perspective in the International Trade of Medicinal Plants Material: An Update.

Science.gov (United States)

Vasisht, Karan; Sharma, Neetika; Karan, Maninder

2016-01-01

The recent years have seen an increased interest in medicinal plants together with the therapeutic use of phytochemicals. Medicinal plants are utilized by the industry for the production of extracts, phytopharmaceuticals, nutraceuticals and cosmeceuticals and their use is expected to grow faster than the conventional drugs. The enormous demand of medicinal plant material has resulted in huge trade both at domestic and international levels. The trade data of medicinal plant material with commodity code HS 1211 (SITC.4, code 292.4) and their derived/related products which are traded under different commodity codes has been acquired from COMTRADE, Trade Map, country reports, technical documents etc for the period 2001 to 2014. The data was analyzed using statistical tools to draw conclusions. The significant features of the global trade; the leading source, consumer, import and export countries; and the striking trends are presented. The trade of the ten key countries and the selected important items is also discussed in detail. The conservative figure of trade of medicinal plants materials and their derived/related products including extracts, essential oils, phytopharmaceuticals, gums, spices used in medicine, tannins for pharmaceutical use, ingredients for cosmetics etc. as calculated from the global export data for the year 2014 is estimated at USD 33 billion. The average global export in medicinal plants under HS 1211 for the fourteen year period was USD 1.92 billion for 601,357 tons per annum and for the year 2014 it stood at 702,813 tons valued at USD 3.60 billion. For the studied period, an annual average growth rate (AAGR) of 2.4% in volumes and 9.2% in values of export was observed. Nearly 30% of the global trade is made up by top two countries of the import and export. China and India from Asia; Egypt and Morocco from Africa; Poland, Bulgaria and Albania from Europe; Chile and Peru from South America are important supply sources. The USA, Japan and Europe

THE PARTICIPATION OF CHARITABLE ORGANIZATIONS IN THE FINANCIAL AND MATERIAL SUPPORT FOR THE INTERNMENT OF UKRAINIAN MILITARY IN POLAND (1920-1921

Directory of Open Access Journals (Sweden)

Artur Babenko

2016-12-01

Full Text Available The article describes the work of charitable organizations in the provision of financial and material assistance to Ukrainian military internees in Poland. Analyzed is the activity of the Ukrainian institutions in attracting international charity. The attention is focused on the activities of the Ukrainian Red Cross.

Scenarios identified internationally for occupational and public exposure to naturally occurring radioactive materials

International Nuclear Information System (INIS)

Fernandez Gomez, Isis Maria

2012-01-01

Natural radiation for decades was considered a normal phenomenon that existed in nature, so that man was conditioned to ignore; unlike artificial ionizing radiation. This mindset has changed, in the late seventies of the last century, because it has became aware of the danger that exposure to natural radiation could pose health. Studies on it have been initiated to conduct and publish. All humans are exposed to natural radiation; but, this exposure is not uniform, has depended on where they live and work, whether they have been in areas with rocks or soils particularly radioactive, their way of life, of the use of certain building materials in their homes, the use of natural gas, the use of home heating with coal. Air travel also have increased exposure to natural radiation. Ionizing radiation, whether natural or artificial, have interacted with the human body in the same way, there fore have failed to say that the natural are less or more harmful than artificial. Natural sources are grouped into two major categories. The first are the external sources: from abroad as cosmic radiation (the sun and interstellar spaces of the universe), terrestrial radiation (emitted by rocks and soil), the radiation of some buildings (e.g. granite, which can emit radon gas) and radiation contained in some foods. The second category are the internal resources: due to the presence in the human body from the environment radionuclides that are able to ionize (potassium-40, carbon-14). The naturally occurring radioactive materials (NORM for its acronym in English) have been referred to those naturally occurring radioactive materials on which any human technological activity has increased its exposure potential compared with the situation unchanged. (author) [es

Legal aspects of the control and repression of illicit trafficking of nuclear and other radioactive materials. Is there a need for an international convention?

International Nuclear Information System (INIS)

Spence, Scott

2012-01-01

It is generally recognised that illicit trafficking of nuclear and other radioactive materials is a serious problem, and one that must be tackled with a comprehensive response involving national governments as well as a number of intergovernmental organisations including the International Atomic Energy Agency (IAEA). The IAEA notes that 1 773 incidents were reported to its Illicit Trafficking Database, or ITDB, between January 1993 and December 2009, and that 351 of these involved '... unauthorized possession and related criminal activities' such as '... illegal possession, movement or attempts to illegally trade in or use nuclear material or radioactive sources'. The IAEA adds that 222 more incidents were confirmed between July 2009 and June 2010 and concludes that: - the availability of unsecured nuclear and other radioactive material persists; - effective border control measures help to detect illicit trafficking, although effective control is not uniformly implemented at all international border points; and - individuals and groups are prepared to engage in trafficking this material. A disturbing trend is trafficking in particularly sensitive regions of the world, such as in countries that were formerly a part of the former Soviet Union. In November 2010, Georgian officials seized four individuals allegedly trying to sell cesium-137, which though fairly common can be used to make a radiological dispersion device (RDD) or 'dirty bomb'. This closely followed a court case in Georgia involving Armenian nationals who had attempted to sell weapon-grade plutonium. More recently, in June 2011, Moldovan police arrested six individuals suspected of trafficking in uranium-235. In view of the problem, this paper considers whether an international convention specifically targeting illicit trafficking is needed or not. The paper does not go conceptually beyond the legal aspects of controlling and repressing illicit trafficking; rather, it will look at whether the existing

Entombment Using Cementitious Materials: Design Considerations and International Experience

Energy Technology Data Exchange (ETDEWEB)

Seitz, Roger Ray

2002-08-01

Cementitious materials have physical and chemical properties that are well suited for the requirements of radioactive waste management. Namely, the materials have low permeability and durability that is consistent with the time frame required for short-lived radionuclides to decay. Furthermore, cementitious materials can provide a long-term chemical environment that substantially reduces the mobility of some long-lived radionuclides of concern for decommissioning (e.g., C-14, Ni-63, Ni-59). Because of these properties, cementitious materials are common in low-level radioactive waste disposal facilities throughout the world and are an attractive option for entombment of nuclear facilities. This paper describes design considerations for cementitious barriers in the context of performance over time frames of a few hundreds of years (directed toward short-lived radionuclides) and time frames of thousands of years (directed towards longer-lived radionuclides). The emphasis is on providing an overview of concepts for entombment that take advantage of the properties of cementitious materials and experience from the design of low-level radioactive waste disposal facilities. A few examples of the previous use of cementitious materials for entombment of decommissioned nuclear facilities and proposals for the use in future decommissioning of nuclear reactors in a few countries are also included to provide global perspective.

Entombment Using Cementitious Materials: Design Considerations and International Experience

Energy Technology Data Exchange (ETDEWEB)

Seitz, R.R.

2002-05-15

Cementitious materials have physical and chemical properties that are well suited for the requirements of radioactive waste management. Namely, the materials have low permeability and durability that is consistent with the time frame required for short-lived radionuclides to decay. Furthermore, cementitious materials can provide a long-term chemical environment that substantially reduces the mobility of some long-lived radionuclides of concern for decommissioning (e.g., C-14, Ni-63, Ni-59). Because of these properties, cementitious materials are common in low-level radioactive waste disposal facilities throughout the world and are an attractive option for entombment of nuclear facilities. This paper describes design considerations for cementitious barriers in the context of performance over time frames of a few hundreds of years (directed toward short-lived radionuclides) and time frames of thousands of years (directed towards longer-lived radionuclides). The emphasis is on providing a n overview of concepts for entombment that take advantage of the properties of cementitious materials and experience from the design of low-level radioactive waste disposal facilities. A few examples of the previous use of cementitious materials for entombment of decommissioned nuclear facilities and proposals for the use in future decommissioning of nuclear reactors in a few countries are also included to provide global perspective.

Entombment Using Cementitious Materials: Design Considerations and International Experience

International Nuclear Information System (INIS)

Seitz, R.R.

2002-01-01

Cementitious materials have physical and chemical properties that are well suited for the requirements of radioactive waste management. Namely, the materials have low permeability and durability that is consistent with the time frame required for short-lived radionuclides to decay. Furthermore, cementitious materials can provide a long-term chemical environment that substantially reduces the mobility of some long-lived radionuclides of concern for decommissioning (e.g., C-14, Ni-63, Ni-59). Because of these properties, cementitious materials are common in low-level radioactive waste disposal facilities throughout the world and are an attractive option for entombment of nuclear facilities. This paper describes design considerations for cementitious barriers in the context of performance over time frames of a few hundreds of years (directed toward short-lived radionuclides) and time frames of thousands of years (directed towards longer-lived radionuclides). The emphasis is on providing a n overview of concepts for entombment that take advantage of the properties of cementitious materials and experience from the design of low-level radioactive waste disposal facilities. A few examples of the previous use of cementitious materials for entombment of decommissioned nuclear facilities and proposals for the use in future decommissioning of nuclear reactors in a few countries are also included to provide global perspective

Scanning personnel for internal deposition of radioactive material with personnel contamination whole body friskers and portal monitors

International Nuclear Information System (INIS)

Lobdell, J.L.

1996-01-01

The potential for using personnel contamination devices such as whole body friskers and portal monitors for internal contamination monitoring was evaluated. Internally deposited radioactive material is typically determined with whole body counting systems. Whole body counts have traditionally been performed on personnel when they report for work, on a periodic basis (i.e., annually), when an uptake is suspected, and on termination. These counts incur significant expense. The monitored personnel pass through whole body friskers and portal monitors daily. This investigation was performed to determine if the external contamination monitors could provide an alternative to the more Costly whole body counting. The ability to detect 1% of a DAC for critical radioisotopes was applied as a detection criteria for this investigation. The results of whole body counts were used to identify the typical internal contamination radionuclides. From this list, the radioisotopes that would be the most difficult to measure were identified. From this review, 60 Co and 131 I were determined to be the critical radionuclides. One percent of a DAC for each isotope was placed, one at a time, in a humanoid phantom. The phantom was placed in the whole body frisker and open-quotes countedclose quotes. The phantom was carried through the portal monitor at a speed equivalent to a person walking through the monitor. Frequency of detection was derived for both systems. Practical aspects of integrating this screening system with traditional internal dosimetry programs are discussed

13th International conference on environmental degradation of materials in nuclear power systems

International Nuclear Information System (INIS)

2007-01-01

The 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems was held on August 19-23, 2007 in Whistler, British Columbia, Canada. More of a scientific meeting than a convention, this conference series is the premier nuclear industry corrosion meeting where the 225 registrations consisted of world experts of the field from utilities, engineering and service organizations, manufacturers, research establishments and universities gathered to listen to 144 technical papers on new work and to explore new insights into corrosion mechanisms in the many water cooled systems in nuclear power plants. Over 225 delegates attended the conference, over 144 technical papers were presented in the following sessions: IASCC; Waste; PWR Secondary; Ni-Base Welds; Operating Experience; Low Alloy Steels; Alloy 800 Steam Generator Tubing; Zirconium Alloys; Crack Growth; SCWR; PWR Primary; BWR SCC; Irradiation Effects; Flow Accelerated Corrosion; and, Nobel Metal

GGVS. Ordinance on road transport of hazardous materials, including the European agreement on international road transport of hazardous materials (ADR), in their wording. Annexes A and B. Ordinances regarding exceptions from GGVS and from the ordinance on rail transport of hazardous materials, GGVE. Reasons. Selected guidelines. List of materials. 6. rev. and enlarged ed.

International Nuclear Information System (INIS)

Ridder, K.

1990-01-01

The brochure contains the following texts: (1) Ordinance on road transport of hazardous materials (GGVS), including the European agreement on international road transport of hazardous materials (ADR), as of 1990: Skeleton ordinance, annexes A and B, reasons given for the first version, and for the first amendment in 1988, execution guidelines - RS 002 (guidelines for executing the ordinance on road transport of hazardous materials, with catalogue of penalties), guidelines for drawing up written instructions for the event of accidents - RS 006, guiding principles for the training of vehicle conductors; (2) ordinance regarding exceptions from the ordinance on road transport of hazardous materials; (3) ordinance regarding exceptions from the ordinance on rail transport of hazardous materials; (4) selected guidelines: Technical guidelines TR IBC K 001, TRS 003, TRS 004, TRS 005, TRS 006; (5) listing of materials and objects governed by the ordinance on hazardous materials transport; (6) catalogue of penalties relative to road transport of hazardous materials. (orig./HP) [de

International inspection activity impacts upon DOE safeguards requirements

International Nuclear Information System (INIS)

Zack, N.R.

1995-01-01

The US has placed certain special nuclear materials declared excess to their strategic needs under international safeguards through the International Atomic Energy Agency (IAEA). This Presidential initiative has obligated materials at several Department of Energy (DOE) facilities for these safeguards activities to demonstrate the willingness of the US to ban production or use of nuclear materials outside of international safeguards. However, IAEA inspection activities generally tend to be intrusive in nature and are not consistent with several domestic safeguards procedures implemented to reduce worker radiation exposures and increase the cost-effectiveness and efficiency of accounting for and storing of special nuclear materials. To help identify and provide workable solutions to these concerns, the Office of Safeguards and Security has conducted a program to determine possible changes to the DOE safeguards and security requirements designed to help facilities under international safeguards inspections more easily comply with domestic safeguards goals during international inspection activities. This paper will discuss the impact of international inspection activities on facility safeguards operations and departmental safeguards procedures and policies

Communication received from the Permanent Mission of Sweden regarding the provision of certain additional information on production, inventories and international transfers of nuclear material and on exports of certain relevant equipment and non-nuclear material

International Nuclear Information System (INIS)

1996-01-01

The document reproduces the text of a note verbale dated 28 June 1996 received by the Director General of IAEA from the Permanent Mission of Sweden through which the Government of Sweden provides, on a voluntary basis, certain additional information on production, inventories and international transfers of nuclear material and on exports of certain relevant equipment and non-nuclear material, in order to assist the Agency in the discharge of its safeguards responsibilities

Reduced cost design of liquid lithium target for international fusion material irradiation facility (IFMIF)

International Nuclear Information System (INIS)

Nakamura, Hiroo; Ida, Mizuho; Sugimoto, Masayoshi; Takeuchi, Hiroshi; Yutani, Toshiaki

2001-01-01

The International Fusion Materials Irradiation Facility (IFMIF) is being jointly planned to provide an accelerator-based D-Li neutron source to produce intense high energy neutrons (2 MW/m 2 ) up to 200 dpa and a sufficient irradiation volume (500 cm 3 ) for testing the candidate materials and components up to about a full lifetime of their anticipated use in ITER and DEMO. To realize such a condition, 40 MeV deuteron beam with a current of 250 mA is injected into high speed liquid lithium flow with a speed of 20 m/s. Following Conceptual Design Activity (1995-1998), a design study with focus on cost reduction without changing its original mission has been done in 1999. The following major changes to the CAD target design have been considered in the study and included in the new design: i) number of the Li target has been changed from 2 to 1, ii) spare of impurity traps of the Li loop was removed although the spare will be stored in a laboratory for quick exchange, iii) building volume was reduced via design changes in lithium loop length. This paper describes the reduced cost design of the lithium target system and recent status of Key Element Technology activities. (author)

Internal radioactive contamination treatment

International Nuclear Information System (INIS)

Tobajas, L. M.

1998-01-01

In a radiological emergency, the internal radioactive contamination becomes a therapeutic urgency and must be established as fast as possible. Just when a radioactive contamination accident occurs, it is difficult to know exactly the amount of radioactive materials absorbed and to estimate the dose received.. The decision to be taken after the incorporation of the radioactive material depends on the method and on the Radiological Protection Department collaboration. Any treatment achieving a reduction of the doses received or expected will be useful. The International Radiological Protection Commission doesn't recommend the use of the dose limit, to decide about the intervention necessity. However the LIA can be used as the reference point to establish the necessity and reach of the treatment. The object of the present work, is to introduce the general principles to carry out the internal people decontamination, under the last international recommendations. (Author) 4 refs

IFMIF (International Fusion Materials Irradiation Facility) key element technology phase task description

Energy Technology Data Exchange (ETDEWEB)

Ida, M.; Nakamura, H.; Sugimoto, M.; Yutani, T.; Takeuchi, H. [eds.] [Japan Atomic Energy Research Inst., Tokai Research Establishment, Fusion Neutron Laboratory, Tokai, Ibaraki (Japan)

2000-08-01

In 2000, a 3 year Key Element technology Phase (KEP) of the International Fusion Materials Irradiation Facility (IFMIF) has been initiated to reduce the key technology risk factors needed to achieve continuous wave (CW) beam with the desired current and energy and to reach the corresponding power handling capabilities in the liquid lithium target system. In the KEP, the IFMIF team (EU, Japan, Russian Federation, US) will perform required tasks. The contents of the tasks are described in the task description sheet. As the KEP tasks, the IFMIF team have proposed 27 tasks for Test Facilities, 12 tasks for Target, 26 tasks for Accelerator and 18 tasks for Design Integration. The task description by RF is not yet available. The task items and task descriptions may be added or revised with the progress of KEP activities. These task description sheets have been compiled in this report. After 3 years KEP, the results of the KEP tasks will be reviewed. Following the KEP, 3 years Engineering Validation Phase (EVP) will continue for IFMIF construction. (author)

IFMIF (International Fusion Materials Irradiation Facility) conceptual design activity reduced cost report

International Nuclear Information System (INIS)

2000-02-01

This report describes the results of a preliminary reevaluation of the design and cost of the International Fusion Materials Irradiation Facility (IFMIF) Project in response to the request from the 28th FPCC meeting in January 1999. Two major ideas have been considered: 1) reduction of the total construction cost through elimination of the previously planned facility upgrade and 2) a facility deployment in 3 stages with capabilities for limited experiments in the first stage. As a result, the size and complexity of the facility could be significantly reduced, leading to substantial cost savings. In addition to these two ideas, this study also included a critical review of the original CDA specification with the objective of elimination of nonessential items. For example, the number of lithium targets was reduced from two to one. As a result of these changes in addition to the elimination of the upgrade, the total cost estimate was very substantially reduced from 797.2 MICF to 487.8 MICF, where 1 MICF = 1 Million of the IFMIF Conversion Units (approximately $1M US January, 1996). (author)

Selected materials of the international workshop on radiation risk and its origin at molecular and cellular level

International Nuclear Information System (INIS)

Pinak, Miroslav

2003-11-01

The workshop ''International Workshop on Radiation Risk and its Origin at Molecular and Cellular Level'' was held at The Tokai Research Establishment, Japan Atomic Energy Research Institute, on the 6th and 7th of February 2003. The Laboratory of Radiation Risk Analysis of JAERI organized it. This international workshop attracted scientists from several different scientific areas, including radiation physics, radiation biology, molecular biology, crystallography of biomolecules, modeling and bio-informatics. Several foreign and domestic keynote speakers addresses the very fundamental areas of radiation risk and tried to establish a link between the fundamental studies at the molecular and cellular level and radiation damages at the organism. The symposium consisted of 13 oral lectures, 10 poster presentations and panel discussion. The 108 participants attended the workshop. This publication comprises of proceedings of oral and poster presentations where available. For the rest of contributions the abstracts or/and selections of presentation materials are shown instead. The 5 papers are indexed individually. (J.P.N.)

International collaborative study for the calibration of proposed International Standards for thromboplastin, rabbit, plain, and for thromboplastin, recombinant, human, plain.

Science.gov (United States)

van den Besselaar, A M H P; Chantarangkul, V; Angeloni, F; Binder, N B; Byrne, M; Dauer, R; Gudmundsdottir, B R; Jespersen, J; Kitchen, S; Legnani, C; Lindahl, T L; Manning, R A; Martinuzzo, M; Panes, O; Pengo, V; Riddell, A; Subramanian, S; Szederjesi, A; Tantanate, C; Herbel, P; Tripodi, A

2018-01-01

Essentials Two candidate International Standards for thromboplastin (coded RBT/16 and rTF/16) are proposed. International Sensitivity Index (ISI) of proposed standards was assessed in a 20-centre study. The mean ISI for RBT/16 was 1.21 with a between-centre coefficient of variation of 4.6%. The mean ISI for rTF/16 was 1.11 with a between-centre coefficient of variation of 5.7%. Background The availability of International Standards for thromboplastin is essential for the calibration of routine reagents and hence the calculation of the International Normalized Ratio (INR). Stocks of the current Fourth International Standards are running low. Candidate replacement materials have been prepared. This article describes the calibration of the proposed Fifth International Standards for thromboplastin, rabbit, plain (coded RBT/16) and for thromboplastin, recombinant, human, plain (coded rTF/16). Methods An international collaborative study was carried out for the assignment of International Sensitivity Indexes (ISIs) to the candidate materials, according to the World Health Organization (WHO) guidelines for thromboplastins and plasma used to control oral anticoagulant therapy with vitamin K antagonists. Results Results were obtained from 20 laboratories. In several cases, deviations from the ISI calibration model were observed, but the average INR deviation attributabled to the model was not greater than 10%. Only valid ISI assessments were used to calculate the mean ISI for each candidate. The mean ISI for RBT/16 was 1.21 (between-laboratory coefficient of variation [CV]: 4.6%), and the mean ISI for rTF/16 was 1.11 (between-laboratory CV: 5.7%). Conclusions The between-laboratory variation of the ISI for candidate material RBT/16 was similar to that of the Fourth International Standard (RBT/05), and the between-laboratory variation of the ISI for candidate material rTF/16 was slightly higher than that of the Fourth International Standard (rTF/09). The candidate materials

What should Marxism materialism propose to International Relations?

Directory of Open Access Journals (Sweden)

Egni Malo

2014-07-01

Full Text Available To argue for the acknowledgment of the importance of historical materialism today when the cold-war and communism have for more than two decades ceased to exist it might create the perception of appearing dejected. Yet such a task which we attempt to take in this work is possible, if only because of the way that our actuality has depicted itself. One can argue for example that the significance of historical materialism as an elucidating method was never reliant on the success of the authoritarian regimes of communism that gave it a face of their own, any more than has traditional conservatism been dependent on social Darwinism, racist or/and aggressive regimes. Beyond this indication we argue of the possibility that historical materialism can be recognised as explanatory system, as one that in derivation and maturity has as its focus of analysis and particularly lays emphasis on what more than ever before governs our social world today, capitalism. The cold war proved the ground or rather the fit for concealing the social and economic divide and made that division namely in competing strategic interest: with the failure of communism and the freeing of historical materialism itself, IR might as well accept the degree to which socio-economic issues determined its agenda and policy of the west.

Analysis of SMELS and reference materials for validation of the k0-based internal monostandard NAA method using in-situ detection efficiency

Science.gov (United States)

Acharya, R.; Swain, K. K.; Reddy, A. V. R.

2010-10-01

Three synthetic multielement standards (SMELS I, II and III) and two reference materials (RMs), SL-3 and Soil-7 of IAEA were analyzed for validation of the k0-based internal monostandard neutron activation analysis (IM-NAA) method utilizing in-situ relative detection efficiency. The internal monostandards used in SMELS and RMs were Au and Sc, respectively. The samples were irradiated in Apsara and Dhruva reactors, BARC and radioactive assay was carried out using a 40% relative efficiency HPGe detector coupled to an 8 k MCA. Concentrations of 23 elements were determined in both SMELS and RMs. In the case of RMs, concentrations of a few elements, whose certified values are not available, could also be determined. The % deviations for the elements determined in SMELS with respect to the assigned values and RMs with respect to certified values were within ±8%. The Z-score values at 95% confidence level for most of the elements in both the materials were within ±1.

Fabrication and Properties of Micro-Nanoencapsulated Phase Change Materials for Internally-Cooled Liquid Desiccant Dehumidification

Directory of Open Access Journals (Sweden)

Xiaofeng Niu

2017-04-01

Full Text Available Micro-nanoencapsulated phase change materials (M-NEPCMs are proposed to be useful in liquid desiccant dehumidification by restraining the temperature rise in the moisture-removal process and improving the dehumidification efficiency. In this paper, the n-octadecane M-NEPCMs with desirable thermal properties for internally-cooled dehumidification were fabricated by using compound emulsifiers through the in-situ polymerization method. Melamine-formaldehyde resin was used as the shell material. The effects of the mixing ratio, emulsification methods and amount of the compound emulsifiers on the morphology, size and thermal properties of the M-NEPCMs were investigated experimentally. The optimum weight mixing ratio of the compound emulsifiers is SDS (sodium dodecyl sulfate:Tween80 (polyoxyethylene sorbitan monooleate:Span80 (sorbitan monooleate = 0.1:0.6:0.3, which achieves the best stability of the n-octadecane emulsion. When the compound emulsifiers are 10 wt. % of the core material, the melting enthalpy of M-NEPCMs reaches its maximum of 145.26 J/g of capsules, with an encapsulation efficiency of 62.88% and a mean diameter of 636 nm. The sub-cooling of the prepared M-NEPCMs is lower than 3 °C, with an acceptable thermal reliability after the thermal cycling test. A pre-emulsification prior to the addition of deionized water in the emulsification is beneficial to the morphology of the capsules, as the phase change enthalpy can be increased by 123.7%.

Fabrication and Properties of Micro-Nanoencapsulated Phase Change Materials for Internally-Cooled Liquid Desiccant Dehumidification.

Science.gov (United States)

Niu, Xiaofeng; Xu, Qing; Zhang, Yi; Zhang, Yue; Yan, Yufeng; Liu, Tao

2017-04-29

Micro-nanoencapsulated phase change materials (M-NEPCMs) are proposed to be useful in liquid desiccant dehumidification by restraining the temperature rise in the moisture-removal process and improving the dehumidification efficiency. In this paper, the n -octadecane M-NEPCMs with desirable thermal properties for internally-cooled dehumidification were fabricated by using compound emulsifiers through the in-situ polymerization method. Melamine-formaldehyde resin was used as the shell material. The effects of the mixing ratio, emulsification methods and amount of the compound emulsifiers on the morphology, size and thermal properties of the M-NEPCMs were investigated experimentally. The optimum weight mixing ratio of the compound emulsifiers is SDS (sodium dodecyl sulfate):Tween80 (polyoxyethylene sorbitan monooleate):Span80 (sorbitan monooleate) = 0.1:0.6:0.3, which achieves the best stability of the n -octadecane emulsion. When the compound emulsifiers are 10 wt. % of the core material, the melting enthalpy of M-NEPCMs reaches its maximum of 145.26 J/g of capsules, with an encapsulation efficiency of 62.88% and a mean diameter of 636 nm. The sub-cooling of the prepared M-NEPCMs is lower than 3 °C, with an acceptable thermal reliability after the thermal cycling test. A pre-emulsification prior to the addition of deionized water in the emulsification is beneficial to the morphology of the capsules, as the phase change enthalpy can be increased by 123.7%.

PREFACE: 7th EEIGM International Conference on Advanced Materials Research

Science.gov (United States)

Joffe, Roberts

2013-12-01

The 7th EEIGM Conference on Advanced Materials Research (AMR 2013) was held at Luleå University of Technology on the 21-22 March 2013 in Luleå, SWEDEN. This conference is intended as a meeting place for researchers involved in the EEIGM programme, in the 'Erasmus Mundus' Advanced Materials Science and Engineering Master programme (AMASE) and the 'Erasmus Mundus' Doctoral Programme in Materials Science and Engineering (DocMASE). This is great opportunity to present their on-going research in the various fields of Materials Science and Engineering, exchange ideas, strengthen co-operation as well as establish new contacts. More than 60 participants representing six countries attended the meeting, in total 26 oral talks and 19 posters were presented during two days. This issue of IOP Conference Series: Materials Science and Engineering presents a selection of articles from EEIGM-7 conference. Following tradition from previous EEIGM conferences, it represents the interdisciplinary nature of Materials Science and Engineering. The papers presented in this issue deal not only with basic research but also with applied problems of materials science. The presented topics include theoretical and experimental investigations on polymer composite materials (synthetic and bio-based), metallic materials and ceramics, as well as nano-materials of different kind. Special thanks should be directed to the senior staff of Division of Materials Science at LTU who agreed to review submitted papers and thus ensured high scientific level of content of this collection of papers. The following colleagues participated in the review process: Professor Lennart Walström, Professor Roberts Joffe, Professor Janis Varna, Associate Professor Marta-Lena Antti, Dr Esa Vuorinen, Professor Aji Mathew, Professor Alexander Soldatov, Dr Andrejs Purpurs, Dr Yvonne Aitomäki, Dr Robert Pederson. Roberts Joffe October 2013, Luleå Conference photograph EEIGM7 conference participants, 22 March 2013 The PDF

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

International Nuclear Information System (INIS)

1979-01-01

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

Proceedings of international symposium on energy materials - opportunities and challenges: book of abstracts

International Nuclear Information System (INIS)

2011-01-01

As a part of its Diamond Jubilee celebrations during 2010-2011, Central Glass and Ceramic Research Institute (CGCRI), Kolkata, a national institute under the Council of Scientific and Industrial Research (CSIR), is organizing a series of symposia and conferences in diversified areas of materials science in general and glass and ceramics in particular. While steady economic growth and sustainable development of the society demands more energy consumption, we are rapidly approaching an era when fossil fuel sources will be largely depleted. Therefore, emphasis should be given to have more innovations in the areas of renewable energy, energy efficiency and new technologies for both energy end-use and supply. Thus, intensive research on alternate/renewable energy sources as well as efficient energy conversion/storage devices are being carried out throughout the world at different research organizations, academic institutions and industries. Under this background, this two-day symposium, International Symposium on Energy Materials Opportunities and Challenges (ISEM-2011), aims at bringing together academicians, scientists and technologists at a common platform providing a unique opportunity to them for communication and collaboration in this area of extreme global importance. The book of abstracts of the contributed papers discusses various aspects of energy which is a subject of core concern in the present age as fossil fuel reserve will soon be exhausted and environmental issues will pose even bigger threat if developments continue to depend only on this source of energy. Papers relevant to INIS are indexed separately

Problems of Chernobyl. Materials of International scientific and practical conference 'Shelter-98'; Problemi Chornobilya. Materyiali Myizhnarodnoyi Naukovo-Praktichnoyi Konferentsyiyi 'Ukrittya-98'

Energy Technology Data Exchange (ETDEWEB)

Klyuchnikov, O O [eds.

1999-07-01

These transactions contain materials of International Scientific and Practical Conference 'Shelter-98', which was held 27-30 November 1998 in Slavutich. They describe the results of the research work of the specialists from Ukraine, neighborhood and far foreign counties. The results, targeted at solving the problems of converting the Shelter Object into oncologically safe state.

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

Analysis of neutron diffraction peak broadening caused by internal stresses in composite materials

International Nuclear Information System (INIS)

Todd, R.I.; Borsa, C.; Derby, B.

1994-01-01

Neutron diffraction is an essential tool in the study of internal stresses in composite materials. In most work only the peak shifts caused by the related elastic strains are considered, but other valuable information exists in the form of peak shape changes. The conditions under which the pure diffraction profile of the composite (i.e. the profile when all sources of broadening not caused by the residual stresses are removed) represents the probability distribution of the peak shifts corresponding to the strains are examined. It is shown that in these conditions, the pure diffraction profile has no attributes of particle size broadening (and vice versa), thereby providing a test for the validity of results interpreted in this way. The experimental derivation of measured strain distributions in Al 2 O 3 /SiCp composites using neutron diffraction is described. No apparent particle size broadening was detected, demonstrating the validity of the results, which also satisfied other tests for consistency

International conference on composite materials and energy: Proceedings. Enercomp 95

International Nuclear Information System (INIS)

Anon.

1995-01-01

World demand for composite materials is continuously increasing. High strength and rigidity, associated with light weight, are the key factors for composites' success. These materials find numerous applications in all sectors of industry. Presently, a sector of particular interest in terms of demand for composite materials is the energy industry. More and more applications are found in the field of the forms of energy: electrical, petroleum, gas, nuclear, solar and wind. The topics addressed in various sessions of the conference cover potential applications of the entire range of polymer, metal and ceramic composites in all sectors of energy. Papers are divided into sessions covering the following topics: properties; design and analysis; fracture; fatigue and long-term performance; new materials; innovative processing; liquid molding; joining and repairs; radiation curing; recycling; development in ceramic materials; innovations in metallic materials; metal-matrix composites; nondestructive evaluation; energy savings in transportation; pressure vessels and piping; wind energy applications; electrical components; concrete applications; power plant applications; and new materials in the energy field. Most of the papers have been processed separately for inclusion on the data base

Proceedings of the international conference on material science: abstract volume

International Nuclear Information System (INIS)

2013-01-01

Materials Science is an interdisciplinary field applying the properties of matter to various areas of science and engineering. This scientific field investigates the relationship between the structure of materials at atomic or molecular scales and their macroscopic properties. In the recent years, materials science has been propelled to the forefront at many universities and research institutions due to the significant advancement on nanoscience and nanotechnology. ICMS-2013 will cover a wide range of interdisciplinary and current research topics related to material science. Research on advanced materials includes nanomaterials, bio-nanomaterials, zero bandgap materials, composites, surface engineering, tissue engineering and biomaterials etc. These materials have numerous applications in electronics, biotechnology, medicine and energy harvesting. The importance of nano-science and nanotechnology has been well documented by both industrial and academic communities worldwide. It is believed that breakthroughs in nano-science and technology will change all aspects of human life in such diverse areas as, electronic devices, energy, biomedicine, sensing, environment, and security etc. Papers relevant to INIS are indexed separately

Introduction to the first International Workshop on the Application of Microporous and Mesoporous Materials as Catalytic Hosts for Fe, Cu an Co

NARCIS (Netherlands)

Donk, van S.; Weckhuysen, B.M.; Kapteijn, F.; Kooyman, P.J.; Hensen, E.J.M.

2005-01-01

This Special Issue of Catalysis Today includes a selection of research presented at the first International Workshop on the ‘Application of Microporous and Mesoporous Materials as Catalytic Hosts for Fe, Cu and Co’, held in Scheveningen, The Netherlands, 1–4 March 2005. This 3-day event welcomed

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

Materials management in an internationally safeguarded fuels reprocessing plant

International Nuclear Information System (INIS)

Hakkila, E.A.; Cobb, D.D.; Dayem, H.A.; Dietz, R.J.; Kern, E.A.; Markin, J.T.; Shipley, J.P.; Barnes, J.W.; Scheinman, L.

1980-04-01

The second volume describes the requirements and functions of materials measurement and accounting systems (MMAS) and conceptual designs for an MMAS incorporating both conventional and near-real-time (dynamic) measurement and accounting techniques. Effectiveness evaluations, based on recently developed modeling, simulation, and analysis procedures, show that conventional accountability can meet IAEA goal quantities and detection times in these reference facilities only for low-enriched uranium. Dynamic materials accounting may meet IAEA goals for detecting the abrupt (1-3 weeks) diversion of 8 kg of plutonium. Current materials accounting techniques probably cannot meet the 1-y protracted-diversion goal of 8 kg for plutonium

PREFACE: 6th EEIGM International Conference on Advanced Materials Research

Science.gov (United States)

Horwat, David; Ayadi, Zoubir; Jamart, Brigitte

2012-02-01

The 6th EEIGM Conference on Advanced Materials Research (AMR 2011) was held at the European School of Materials Engineering (EEIGM) on the 7-8 November 2011 in Nancy, France. This biennial conference organized by the EEIGM is a wonderful opportunity for all scientists involved in the EEIGM programme, in the 'Erasmus Mundus' Advanced Materials Science and Engineering Master programme (AMASE) and the 'Erasmus Mundus' Doctoral Programme in Materials Science and Engineering (DocMASE), to present their research in the various fields of Materials Science and Engineering. This conference is also open to other universities who have strong links with the EEIGM and provides a forum for the exchange of ideas, co-operation and future orientations by means of regular presentations, posters and a round-table discussion. This edition of the conference included a round-table discussion on composite materials within the Interreg IVA project '+Composite'. Following the publication of the proceedings of AMR 2009 in Volume 5 of this journal, it is with great pleasure that we present this selection of articles to the readers of IOP Conference Series: Materials Science and Engineering. Once again it represents the interdisciplinary nature of Materials Science and Engineering, covering basic and applicative research on organic and composite materials, metallic materials and ceramics, and characterization methods. The editors are indebted to all the reviewers for reviewing the papers at very short notice. Special thanks are offered to the sponsors of the conference including EEIGM-Université de Lorraine, AMASE, DocMASE, Grand Nancy, Ville de Nancy, Region Lorraine, Fédération Jacques Villermaux, Conseil Général de Meurthe et Moselle, Casden and '+Composite'. Zoubir Ayadi, David Horwat and Brigitte Jamart

Current technical issues in international safeguards

International Nuclear Information System (INIS)

Bennett, C.A.

1977-01-01

Safeguards systems, and the associated need for technical and systems development, reflect changing conditions and concerns associated with the nuclear fuel cycle and the safety and security of nuclear materials and facilities. In particular, the implementation of international safeguards has led to the recognition of certain technical issues, both old and new, which are in need of resolution. These are: 1. The grading of nuclear materials and facilities with respect to their relative safeguards significance. 2. The extension and upgrading of safeguards techniques to maintain adequate protection in view of constantly increasing amounts of material to be safeguarded. 3. The balance between safeguards mechanisms based on physical protection and material accounting, and the role of surveillance and containment in each case. 4. The role of information systems as a basis for both analytical feedback and the determination of the factors affecting system effectiveness and their interrelationship. 5. A determination of the degree to which the overall technical effectiveness of international inspection activities can be quantified. Each of these technical issues must be considered in light of the specific objectives of international safeguards, which differ from domestic safeguards in terms of the level of the threat, the safeguards mechanisms available, and the diversion strategies assumed. Their resolution in this international context is essential if the effectiveness and viability of international safeguards are to be maintained

International SSAC training courses

Energy Technology Data Exchange (ETDEWEB)

Bates, O G

1988-01-01

State Systems of Accounting for and Control of Nuclear Material (SSACs) are a vital element in achieving effectiveness and creativity for international safeguards. A nation's SSAC must also satisfy national objectives, such as accounting for all safeguarded material and detecting losses or unauthorized removal of material. In recent years the Agency has placed an increasing emphasis on assisting Member States in developing their state system of accountancy and control of nuclear material.

International SSAC training courses

International Nuclear Information System (INIS)

Bates, O.G.

1988-01-01

State Systems of Accounting for and Control of Nuclear Material (SSACs) are a vital element in achieving effectiveness and creativity for international safeguards. A nation's SSAC must also satisfy national objectives, such as accounting for all safeguarded material and detecting losses or unauthorized removal of material. In recent years the Agency has placed an increasing emphasis on assisting Member States in developing their state system of accountancy and control of nuclear material

Dielectric material in lead-based perovskite and fabrication process for multilayer ceramic capacitor with copper internal electrode

International Nuclear Information System (INIS)

Kato, J.; Yokotani, Y.; Kagata, H.; Nakatani, S.; Kugimiya, K.

1990-01-01

This paper reports on the development of a multilayer ceramic capacitor with copper internal electrodes. Dielectric materials of the capacitor is lead- based perovskite (Pb a Ca b ) (Mg 1/3 Nb 2/3 ) x Ti y (Ni 1/2 W 1/2 ) z O 2 + a + b where a + b gt 1 and x + y + z = 1. The materials can be fired below 1000 degrees C and have high resistivity even when fired in the atmosphere below the equilibrium oxygen partial pressure of copper and CuO. The fabrication process of the capacitor has following features. The electrode paste is composed of copper oxide to prevent breaking of the laminated body in a burn out process. Then the copper oxide is first metalized and fired in a controlled atmosphere. The obtained capacitor of 20 dielectric layers of 17 micron meter meets to Z5U specification and has low loss tangent of 0.6% and stability under d.c. bias voltage and high a.c. field

Transport of radioactive materials by post

International Nuclear Information System (INIS)

1984-11-01

The objective of the Seminar was to encourage safe and efficient carriage of radioactive material by post. Adequate, up-to-date regulations for international and domestic shipment of radioactive material by all modes of transport, including by mail, have been published by the IAEA. UPU, ICAO, IATA and other international organizations as well as a majority of the countries of the world have adopted most sections of the Agency's Regulations for the Safe Transport of Radioactive Material. Although there is an apparent need for shipping radioactive material by mail, some countries allow only domestic shipments and the postal regulations applied in these countries often differs from the international regulations. Only about 25 countries are known to allow international (as well as domestic) shipments. From the discussions and comments at the Seminar, it appears that the option of shipment by post would be advantageous to enhance both the safety and economy of transporting, as well as to increase availability of, radioactive materials. The Agency's Regulations for transport by post as adopted by the UPU and ICAO are considered to provide a high level of safety and ensure a negligible element of risk. A more uniform application of these regulations within UPU Member States should be encouraged. The competent authority for implementation of the other parts of the Agency's Regulations in each of the Member States should be invited to advise the Postal Administrators and assist in applying the requirements to national as well as international postal shipments

77 FR 49167 - Hazardous Materials: Harmonization with International Standards (RRR)

Science.gov (United States)

2012-08-15

..., but are not limited to, the authorization to allow wood as a material of package construction for... to the regulated community with respect to the material of construction authorized for such packages... amendments include, but are not limited to, the authorization to use wood as a material of package...

Technical committee meeting on material-coolant interactions and material movement and relocation in liquid metal fast reactors

International Nuclear Information System (INIS)

1994-01-01

The Technical Committee Meeting on Material-Coolant Interactions and Material Movement and Relocation in Liquid Metal Fast Reactors was sponsored by the International Working Group on Fast Reactors (IWGFR), International Atomic Energy Agency (IAEA) and hosted by PNC, on behalf of the Japanese government. A broad range of technical subjects was discussed in the TCM, covering entire aspects of material motion and interactions relevant to the safety of LMFRs. Recent achievement and current status in research and development in this area were presented including European out-of-pile test of molten material movement and relocation; molten material-sodium interaction; molten fuel-coolant interaction; core disruptive accidents; sodium boiling; post accident material relocation, heat removal and relevant experiments already performed or planned

Technical committee meeting on material-coolant interactions and material movement and relocation in liquid metal fast reactors

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-07-01

The Technical Committee Meeting on Material-Coolant Interactions and Material Movement and Relocation in Liquid Metal Fast Reactors was sponsored by the International Working Group on Fast Reactors (IWGFR), International Atomic Energy Agency (IAEA) and hosted by PNC, on behalf of the Japanese government. A broad range of technical subjects was discussed in the TCM, covering entire aspects of material motion and interactions relevant to the safety of LMFRs. Recent achievement and current status in research and development in this area were presented including European out-of-pile test of molten material movement and relocation; molten material-sodium interaction; molten fuel-coolant interaction; core disruptive accidents; sodium boiling; post accident material relocation, heat removal and relevant experiments already performed or planned.

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

Material efficiency: providing material services with less material production.

Science.gov (United States)

Allwood, Julian M; Ashby, Michael F; Gutowski, Timothy G; Worrell, Ernst

2013-03-13

Material efficiency, as discussed in this Meeting Issue, entails the pursuit of the technical strategies, business models, consumer preferences and policy instruments that would lead to a substantial reduction in the production of high-volume energy-intensive materials required to deliver human well-being. This paper, which introduces a Discussion Meeting Issue on the topic of material efficiency, aims to give an overview of current thinking on the topic, spanning environmental, engineering, economics, sociology and policy issues. The motivations for material efficiency include reducing energy demand, reducing the emissions and other environmental impacts of industry, and increasing national resource security. There are many technical strategies that might bring it about, and these could mainly be implemented today if preferred by customers or producers. However, current economic structures favour the substitution of material for labour, and consumer preferences for material consumption appear to continue even beyond the point at which increased consumption provides any increase in well-being. Therefore, policy will be required to stimulate material efficiency. A theoretically ideal policy measure, such as a carbon price, would internalize the externality of emissions associated with material production, and thus motivate change directly. However, implementation of such a measure has proved elusive, and instead the adjustment of existing government purchasing policies or existing regulations-- for instance to do with building design, planning or vehicle standards--is likely to have a more immediate effect.

A thermomechanical constitutive model for cemented granular materials with quantifiable internal variables. Part II - Validation and localization analysis

Science.gov (United States)

Das, Arghya; Tengattini, Alessandro; Nguyen, Giang D.; Viggiani, Gioacchino; Hall, Stephen A.; Einav, Itai

2014-10-01

We study the mechanical failure of cemented granular materials (e.g., sandstones) using a constitutive model based on breakage mechanics for grain crushing and damage mechanics for cement fracture. The theoretical aspects of this model are presented in Part I: Tengattini et al. (2014), A thermomechanical constitutive model for cemented granular materials with quantifiable internal variables, Part I - Theory (Journal of the Mechanics and Physics of Solids, 10.1016/j.jmps.2014.05.021). In this Part II we investigate the constitutive and structural responses of cemented granular materials through analyses of Boundary Value Problems (BVPs). The multiple failure mechanisms captured by the proposed model enable the behavior of cemented granular rocks to be well reproduced for a wide range of confining pressures. Furthermore, through comparison of the model predictions and experimental data, the micromechanical basis of the model provides improved understanding of failure mechanisms of cemented granular materials. In particular, we show that grain crushing is the predominant inelastic deformation mechanism under high pressures while cement failure is the relevant mechanism at low pressures. Over an intermediate pressure regime a mixed mode of failure mechanisms is observed. Furthermore, the micromechanical roots of the model allow the effects on localized deformation modes of various initial microstructures to be studied. The results obtained from both the constitutive responses and BVP solutions indicate that the proposed approach and model provide a promising basis for future theoretical studies on cemented granular materials.

Internal dosimetry technical basis manual

International Nuclear Information System (INIS)

1990-01-01

The internal dosimetry program at the Savannah River Site (SRS) consists of radiation protection programs and activities used to detect and evaluate intakes of radioactive material by radiation workers. Examples of such programs are: air monitoring; surface contamination monitoring; personal contamination surveys; radiobioassay; and dose assessment. The objectives of the internal dosimetry program are to demonstrate that the workplace is under control and that workers are not being exposed to radioactive material, and to detect and assess inadvertent intakes in the workplace. The Savannah River Site Internal Dosimetry Technical Basis Manual (TBM) is intended to provide a technical and philosophical discussion of the radiobioassay and dose assessment aspects of the internal dosimetry program. Detailed information on air, surface, and personal contamination surveillance programs is not given in this manual except for how these programs interface with routine and special bioassay programs

Internal dosimetry technical basis manual

Energy Technology Data Exchange (ETDEWEB)

1990-12-20

The internal dosimetry program at the Savannah River Site (SRS) consists of radiation protection programs and activities used to detect and evaluate intakes of radioactive material by radiation workers. Examples of such programs are: air monitoring; surface contamination monitoring; personal contamination surveys; radiobioassay; and dose assessment. The objectives of the internal dosimetry program are to demonstrate that the workplace is under control and that workers are not being exposed to radioactive material, and to detect and assess inadvertent intakes in the workplace. The Savannah River Site Internal Dosimetry Technical Basis Manual (TBM) is intended to provide a technical and philosophical discussion of the radiobioassay and dose assessment aspects of the internal dosimetry program. Detailed information on air, surface, and personal contamination surveillance programs is not given in this manual except for how these programs interface with routine and special bioassay programs.

Positron annihilation lifetime spectroscopy (PALS) application in metal barrier layer integrity for porous low- k materials

CERN Document Server

Simon, Lin; Gidley, D W; Wetzel, J T; Monnig, K A; Ryan, E T; Simon, Jang; Douglas, Yu; Liang, M S; En, W G; Jones, E C; Sturm, J C; Chan, M J; Tiwari, S C; Hirose, M

2002-01-01

Positron Annihilation Lifetime Spectroscopy (PALS) is a useful tool to pre-screen metal barrier integrity for Si-based porous low-k dielectrics. Pore size of low-k, thickness of metal barrier Ta, positronium (Ps) leakage from PALS, trench sidewall morphology, electrical test from one level metal (1LM) pattern wafer and Cu diffusion analysis were all correlated. Macro-porous low-k (pore size >=200 AA) and large scale meso-porous low-k (>50~200 AA) encounter both Ps leakage and Cu diffusion into low-k dielectric in the 0.25 mu mL/0.3 mu mS structures when using SEMATECH in-house PVD Ta 250 AA as barrier layer. For small scale meso-porous (>20~50 AA) and micro- porous (<=20 AA) low-k, no Ps leakage and no Cu diffusion into low-k were observed even with PVD Ta 50 AA, which is proved also owing to sidewall densification to seal all sidewall pores due to plasma etch and ash. For future technology, smaller pore size of porous Si-based low-k (=<50 AA) will be preferential for dense low-k like trench sidewall to...

Effects of radiation rays on construction materials

International Nuclear Information System (INIS)

Akkurt, I.; Kilicarslan, S.; Basyigit, C.; Kacar, A.

2006-01-01

Molecules that are bring into existence material determined as gas, liquid and stiff according to their internal structures and heat. Materials show various reaction to various effects that is result from all kind of materials have various internal structures. Radiation is covert materials' mechanical, physical and chemical properties. Nowadays in construction formation there isn't using only one material it is preferred that kind of materials composition because of there are run into some problems about choosing and decision sort of material. Material that using in construction is classified as metals, plastics and ceramics in three groups. About sixty percent of construction cost is being formed from construction materials. In this study effects of various radiations on construction materials are being investigated and the end of study it is being suggestion some useful construction materials according to usage land and radiation properties

Effect of Surface Modification and Macrophage Phenotype on Particle Internalization

Energy Technology Data Exchange (ETDEWEB)

Wang, Daniel [Iowa State University; Phan, Ngoc [Iowa State University; Isely, Christopher [Iowa State University; Bruene, Lucas [Iowa State University; Bratlie, Kaitlin M [Ames Laboratory

2014-11-10

Material properties play a key role in the cellular internalization of polymeric particles. In the present study, we have investigated the effects of material characteristics such as water contact angle, zeta potential, melting temperature, and alternative activation of complement on particle internalization for pro-inflammatory, pro-angiogenic, and naïve macrophages by using biopolymers (~600 nm), functionalized with 13 different molecules. Understanding how material parameters influence particle internalization for different macrophage phenotypes is important for targeted delivery to specific cell populations. Here, we demonstrate that material parameters affect the alternative pathway of complement activation as well as particle internalization for different macrophage phenotypes. Here, we show that the quantitative structure–activity relationship method (QSAR) previously used to predict physiochemical properties of materials can be applied to targeting different macrophage phenotypes. These findings demonstrated that targeted drug delivery to macrophages could be achieved by exploiting material parameters.

King post truss as a motif for internal structure of (meta)material with controlled elastic properties

Science.gov (United States)

Turco, Emilio; Giorgio, Ivan; Misra, Anil; dell'Isola, Francesco

2017-10-01

One of the most interesting challenges in the modern theory of materials consists in the determination of those microstructures which produce, at the macro-level, a class of metamaterials whose elastic range is many orders of magnitude wider than the one exhibited by `standard' materials. In dell'Isola et al. (2015 Zeitschrift für angewandte Mathematik und Physik 66, 3473-3498. (doi:10.1007/s00033-015-0556-4)), it was proved that, with a pantographic microstructure constituted by `long' micro-beams it is possible to obtain metamaterials whose elastic range spans up to an elongation exceeding 30%. In this paper, we demonstrate that the same behaviour can be obtained by means of an internal microstructure based on a king post motif. This solution shows many advantages: it involves only microbeams; all constituting beams are undergoing only extension or compression; all internal constraints are terminal pivots. While the elastic deformation energy can be determined as easily as in the case of long-beam microstructure, the proposed design seems to have obvious remarkable advantages: it seems to be more damage resistant and therefore to be able to have a wider elastic range; it can be realized with the same three-dimensional printing technology; it seems to be less subject to compression buckling. The analysis which we present here includes: (i) the determination of Hencky-type discrete models for king post trusses, (ii) the application of an effective integration scheme to a class of relevant deformation tests for the proposed metamaterial and (iii) the numerical determination of an equivalent second gradient continuum model. The numerical tools which we have developed and which are presented here can be readily used to develop an extensive measurement campaign for the proposed metamaterial.

Materials characterisation

International Nuclear Information System (INIS)

Azali Muhammad

2005-01-01

Various nuclear techniques have been developed and employed by technologies and scientists worldwide to physically and chemically characterise the material particularly those that have applications in industry. These include small angle neutron scattering (SANS), x-ray diffraction (XRD), scanning electron microscope (SEM) and transmission electron microscope (TEM) for the internal structural study of material, whereas, the x-ray fluorescence (XRF) for the chemical analysis, while the Moessbauer spectroscopy for the study on the magnetic properties and structural identity of material. Basic principle and instrumentations of the techniques are discussed in this chapter. Example of their applications in various disciplines particularly in characterisation of industrial materials also described

International collaborative study for the calibration of proposed International Standards for thromboplastin, rabbit, plain and for thromboplastin, recombinant, human, plain

DEFF Research Database (Denmark)

van den Besselaar, A M H P; Chantarangkul, V; Angeloni, F

2018-01-01

BACKGROUND: The availability of International Standards for thromboplastin is essential for the calibration of routine reagents and hence the calculation of the International Normalized Ratio (INR). Stocks of the current 4(th) International Standards are running low. Candidate replacement materia......) international standard (rTF/09). The candidate materials have been accepted by WHO as the 5(th) International Standards for thromboplastin, rabbit plain, and thromboplastin, recombinant, human, plain. This article is protected by copyright. All rights reserved.......BACKGROUND: The availability of International Standards for thromboplastin is essential for the calibration of routine reagents and hence the calculation of the International Normalized Ratio (INR). Stocks of the current 4(th) International Standards are running low. Candidate replacement materials...... have been prepared. This report describes the calibration of the proposed 5(th) International Standards for thromboplastin, rabbit, plain (coded RBT/16) and for thromboplastin, recombinant, human, plain (coded rTF/16). METHODS: An international collaborative study was carried out for the assignment...

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

Process for the manufacture of a filter material for cleaning industrial or internal combustion engine exhaust gases and filter material manufactured according to the process. Verfahren zur Herstellung eines Filterstoffes zur Reinigung von industriellen oder Brennkraftmaschinen-Abgasen und ein hiernach hergestellter Filterstoff

Energy Technology Data Exchange (ETDEWEB)

Bumbalek, A.

1986-01-02

This is a process for the manufacture of a filter material for cleaning industrial or internal combustion engine exhaust gases and filter material manufactured according to the process. The filter material is manufactured from the mineralized combustion product of peel of tropical fruits burnt at a temperature of 820/sup 0/C to 840/sup 0/C in an oxidising atmosphere excluding the production of carbon, particularly using banana skins and orange peels, which product is granulated with carrier materials or compressed.

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.

PREFACE: International Symposium on Materials Science and Innovation for Sustainable Society - Eco-Materials and Eco-Innovation for Global Sustainability - The 21st Iketani Conference 2011

Science.gov (United States)

Takahashi, Yasuo

2012-08-01

Conference logo The 21st century has been called the century of environmental revolution. Green innovations and environmentally friendly production systems based on physics, chemistry, materials science, and electronic engineering will be indispensable for ensuring renewable energy and establishing a sustainable society. In particular, production design, materials processing, and fabrication technologies such as welding and joining will be very important components of such green innovations. For these reasons, the International Symposium on Materials Science and Innovation for Sustainable Society - eco-materials and eco-innovation for global sustainability - (ECO-MATES 2011) was organized by the Joining and Welding Research Institute (JWRI) and the Center of Environmental Innovation Design for Sustainability (CEIDS), Osaka University. ECO-MATES 2011 was held at Hotel Hankyu Expo Park, Osaka, Japan from 28-30 November 2011. 435 participants from 20 countries around the world attended the symposium. 149 oral presentations including 60 invited talks and 160 posters were presented at the symposium to discuss the latest research and developments in green innovations in relation to environmental issues. The topics of the symposium covered all environmentally related fields including renewable energy, energy-materials, environment and resources, waste and biomass, power electronics, semiconductor, rare-earth metals, functional materials, organic electronics materials, electronics packaging, smart processing, joining and welding, eco-efficient processes, and green applied physics and chemistry. Therefore, 55 full papers concerning green innovations and environmentally benign production were selected and approved by the editorial board and the program committee of ECO-MATES 2011. All papers were accepted through peer review processes. I believe that all the papers have many informative contents. On behalf of the steering committee of the symposium, I would like to express

PREFACE: 17th International Conference on Microscopy of Semiconducting Materials 2011

Science.gov (United States)

Walther, T.; Midgley, P. A.

2011-11-01

This volume contains invited and contributed papers from the 17th international conference on 'Microscopy of Semiconducting Materials' held at Churchill College, University of Cambridge, on 4-7 April 2011. The meeting was organised under the auspices of the Institute of Physics and supported by the Royal Microscopical Society as well as the Materials Research Society of the USA. This conference series deals with recent advances in semiconductor studies carried out by all forms of microscopy, with an emphasis on electron microscopy and related techniques with high spatial resolution. This time the meeting was attended by 131 delegates from 25 countries world-wide, a record in terms of internationality. As semiconductor devices shrink further new routes of device processing and characterisation need to be developed, and, for the latter, methods that offer sub-nanometre spatial resolution are particularly valuable. The various forms of imaging, diffraction and spectroscopy available in modern microscopes are powerful tools for studying the microstructure, the electronic structure, the chemistry and also electric fields in semiconducting materials. Recent advances in instrumentation, from lens aberration correction in both TEM and STEM instruments, to the development of a wide range of scanning probe techniques, as well as new methods of signal quantification have been presented at this conference. Two examples of topics at this meeting that have attracted a number of interesting studies were: the correlation of microstructural, optical and chemical information at atomic resolution with nanometre-scale resolved maps of the local electrical fields in (In,Al)GaN based semiconductors and tomographic approaches to characterise ensembles of nanowires and stacks of processed layers in devices Figure 1 Figure 1. Opening lecture by Professor Sir Colin J Humphreys. Each manuscript submitted for publication in this proceedings volume has been independently reviewed and revised

Results from the CDE phase activity on neutron dosimetry for the international fusion materials irradiation facility test cell

CERN Document Server

Esposito, B; Maruccia, G; Petrizzi, L; Bignon, G; Blandin, C; Chauffriat, S; Lebrun, A; Recroix, H; Trapp, J P; Kaschuck, Y

2000-01-01

The international fusion materials irradiation facility (IFMIF) project deals with the study of an accelerator-based, deuterium-lithium source, producing high energy neutrons at sufficient intensity and irradiation volume to test samples of candidate materials for fusion energy reactors. IFMIF would also provide calibration and validation of data from fission reactor and other accelerator based irradiation tests. This paper describes the activity on neutron/gamma dosimetry (necessary for the characterization of the specimens' irradiation) performed in the frame of the IFMIF conceptual design evaluation (CDE) neutronics tasks. During the previous phase (conceptual design activity (CDA)) the multifoil activation method was proposed for the measurement of the neutron fluence and spectrum and a set of suitable foils was defined. The cross section variances and covariances of this set of foils have now been used for tests on the sensitivity of the IFMIF neutron spectrum determination to cross section uncertainties...

Dossier: transport of radioactive materials

International Nuclear Information System (INIS)

Mignon, H.; Brachet, Y.; Turquet de Beauregard, G.; Mauny, G.; Robine, F.; Plantet, F.; Pestel Lefevre, O.; Hennenhofer, G.; Bonnemains, J.

1997-01-01

This dossier is entirely devoted to the transportation of radioactive and fissile materials of civil use. It comprises 9 papers dealing with: the organization of the control of the radioactive materials transport safety (safety and security aspects, safety regulations, safety analysis and inspection, emergency plans, public information), the technical aspects of the regulation concerning the transport of radioactive materials (elaboration of regulations and IAEA recommendations, risk assessments, defense in depth philosophy and containers, future IAEA recommendations, expertise-research interaction), the qualification of containers (regulations, test facilities), the Transnucleaire company (presentation, activity, containers for spent fuels), the packages of radioactive sources for medical use (flux, qualification, safety and transport), an example of accident during radioactive materials transportation: the Apach train derailment (February 4, 1997), the sea transport of radioactive materials (international maritime organization (OMI), international maritime dangerous goods (IMDG) code, irradiated nuclear fuel (INF) safety rules), the transport of radioactive materials in Germany, and the point of view from an external observer. (J.S.)

PREFACE: International Conference on Functional Materials and Nanotechnologies 2013 (FM&NT2013)

Science.gov (United States)

Nõmmiste, Ergo; Kirm, Marco; Plank, Toomas

2013-12-01

The International Conference Functional Materials and Nanotechnologies (FM&NT - 2013) was held in Tartu, 21-24 April 2013 at the Dorpat Conference Centre. The conference was organised by Institute of Physics, University of Tartu. The FM&NT conference series was started in 2006 by scientists from the Institute of Solid State Physics, University of Latvia. It is an annual conference bringing together researchers from the whole world. The warm and open atmosphere of this scientific conference has turned it into event where people from different fields meet under the common name of functional materials and nanotechnology. It is particularly important for early stage scientists who are looking for new knowledge and contact with people from various fields. Our Latvian colleagues with their success in internationalization made us neighbouring Estonians so envious that we could not withstand proposing that we host the conference in every second year in Estonia. Actually this is in a way the continuation of the idea of the famous Baltic seminars which took place over several decades during the last century. Due to political constraints these seminars were only opened to scientist of the former Eastern European countries, but which were extremely popular and attracted attendees from over the whole Soviet Union. Much fruitful cooperation started from the initial personal contacts of scientists at these seminars held twice per year, once in Latvia and the second time in Estonia. At the last FM&NT 2012 conference, the decision was made that Institute of Physics, University of Tartu would organise the event in Tartu in 2013. Along with traditional topics such as multifunctional materials, nanomaterials, materials for sustainable energy applications and theory, this conference focused on studies using synchrotron radiation and other novel light sources. The number of registered participants from 21 countries was nearly 300. During the three days of the conference 14 invited, 45

Radioactive material air transportation; Transporte aereo de material radioativo

Energy Technology Data Exchange (ETDEWEB)

Pader y Terry, Claudio Cosme [Varig Logistica (VARIGLOG), Sao Paulo, SP (Brazil)

2002-07-01

As function of the high aggregated value, safety regulations and the useful life time, the air transportation has been used more regularly because is fast, reliable, and by giving great security to the cargo. Based on the International Atomic Energy Agency (IAEA), the IATA (International Air Transportation Association) has reproduced in his dangerous goods manual (Dangerous Goods Regulations - DGR IATA), the regulation for the radioactive material air transportation. Those documents support this presentation.

A thermomechanical constitutive model for cemented granular materials with quantifiable internal variables. Part I-Theory

Science.gov (United States)

Tengattini, Alessandro; Das, Arghya; Nguyen, Giang D.; Viggiani, Gioacchino; Hall, Stephen A.; Einav, Itai

2014-10-01

This is the first of two papers introducing a novel thermomechanical continuum constitutive model for cemented granular materials. Here, we establish the theoretical foundations of the model, and highlight its novelties. At the limit of no cement, the model is fully consistent with the original Breakage Mechanics model. An essential ingredient of the model is the use of measurable and micro-mechanics based internal variables, describing the evolution of the dominant inelastic processes. This imposes a link between the macroscopic mechanical behavior and the statistically averaged evolution of the microstructure. As a consequence this model requires only a few physically identifiable parameters, including those of the original breakage model and new ones describing the cement: its volume fraction, its critical damage energy and bulk stiffness, and the cohesion.

Materials Science Laboratory

Science.gov (United States)

Jackson, Dionne

2005-01-01

The NASA Materials Science Laboratory (MSL) provides science and engineering services to NASA and Contractor customers at KSC, including those working for the Space Shuttle. International Space Station. and Launch Services Programs. These services include: (1) Independent/unbiased failure analysis (2) Support to Accident/Mishap Investigation Boards (3) Materials testing and evaluation (4) Materials and Processes (M&P) engineering consultation (5) Metrology (6) Chemical analysis (including ID of unknown materials) (7) Mechanical design and fabrication We provide unique solutions to unusual and urgent problems associated with aerospace flight hardware, ground support equipment and related facilities.

International operations networks

CERN Document Server

Farooq, Sami; Cheng, Yang

2014-01-01

Although the area of International Manufacturing Network (IMN) and International Operations Network (ION) has received considerable attention in the literature, most of studies appear multifaceted and interdisciplinary, and thereby require thorough investigation from both academic and practical perspectives, in order to deepen our related understanding. The book seeks advanced contributions that will combine theoretical insights and empirical experience by offering a detailed examination of IMN and, further, ION from various perspectives. This book can be used as a reference material for scholarpractitioners, business executives, and university researchers who need to deepen their understanding on the importance and influence of IMN and ION as well as their development. The book is important because there are few reference/resource materials available related to IMN and ION.

International Nuclear Security

Energy Technology Data Exchange (ETDEWEB)

Doyle, James E. [Los Alamos National Laboratory

2012-08-14

This presentation discusses: (1) Definitions of international nuclear security; (2) What degree of security do we have now; (3) Limitations of a nuclear security strategy focused on national lock-downs of fissile materials and weapons; (4) What do current trends say about the future; and (5) How can nuclear security be strengthened? Nuclear security can be strengthened by: (1) More accurate baseline inventories; (2) Better physical protection, control and accounting; (3) Effective personnel reliability programs; (4) Minimize weapons-usable materials and consolidate to fewer locations; (5) Consider local threat environment when siting facilities; (6) Implement pledges made in the NSS process; and (7) More robust interdiction, emergency response and special operations capabilities. International cooperation is desirable, but not always possible.

PREFACE: The 16th International Symposium on Boron, Borides and Related Materials (ISBB 2008)

Science.gov (United States)

Tanaka, Takaho

2009-07-01

This volume of Journal of Physics: Conference Series contains invited and contributed peer-reviewed papers that were presented at the 16th International Symposium on Boron, Borides and Related Materials (ISBB 2008), which was held on 7-12 September 2008, at Kunibiki Messe, Matsue, Japan. This triennial symposium has a half-century long history starting from the 1st meeting in 1959 at Asbury Park, New Jersey. We were very pleased to organize ISBB 2008, which gathered chemists, physicists, materials scientists as well as diamond and high-pressure researchers. This meeting had a strong background in the boron-related Japanese research history, which includes the discovery of superconductivity in MgB2 and development of Nd-Fe-B hard magnets and of YB66 soft X-ray monochromator. The scope of ISBB 2008 spans both basic and applied interdisciplinary research that is centered on boron, borides and related materials, and the collection of articles defines the state of the art in research on these materials. The topics are centered on: 1. Preparation of new materials (single crystals, thin films, nanostructures, ceramics, etc) under normal or extreme conditions. 2. Crystal structure and chemical bonding (new crystal structures, nonstoichiometry, defects, clusters, quantum-chemical calculations). 3. Physical and chemical properties (band structure, phonon spectra, superconductivity; optical, electrical, magnetic, emissive, mechanical properties; phase diagrams, thermodynamics, catalytic activity, etc) in a wide range of temperatures and pressures. 4. Applications and prospects (thermoelectric converters, composites, ceramics, coatings, etc) There were a few discoveries of new materials, such as nanomaterials, and developments in applications. Many contributions were related to 4f heavy Fermion systems of rare-earth borides. Exotic mechanisms of magnetism and Kondo effects have been discussed, which may indicate another direction of development of boride. Two special sessions

Applications: Accelerators for new materials

International Nuclear Information System (INIS)

Andersen, H.H.

1990-01-01

Ion beams bring important benefits to material processing, and the Seventh International Conference on Ion Beam Modification of Materials (IBMM 90), held in Knoxville, Tennessee, in September showed the promising progress being made

Applications: Accelerators for new materials

Energy Technology Data Exchange (ETDEWEB)

Andersen, H. H. [Copenhagen (Denmark)

1990-12-15

Ion beams bring important benefits to material processing, and the Seventh International Conference on Ion Beam Modification of Materials (IBMM 90), held in Knoxville, Tennessee, in September showed the promising progress being made.

International physical protection standards: support for development and implementation

International Nuclear Information System (INIS)

Soo Hoo, M.S.

2002-01-01

Full text: Since 1972, the IAEA has been a recognized organization in promoting the development of international standards on the physical protection of nuclear materials. This responsibility has continued through the present in the 1999 publication of the fourth revision of INFCIRC/225, the physical protection of nuclear material and nuclear facilities and in being the repository for the convention on the physical protection of nuclear material which was originally published in 1980 as INFCIRC/274. The IAEA has also published other reference documents in support these two standards. With changing world events and greater concern for the physical protection of nuclear materials and facilities, IAEA member states have increased IAEA physical protection responsibilities. Currently, the IAEA is serving as the secretariat for drafting revisions to the physical protection convention. The proposed revisions will strengthen international physical protection standards through the incorporation of physical protection fundamentals that should apply to all nuclear materials in international or domestic use, storage and transport. Furthermore, the physical protection fundamentals would also extend to include nuclear facilities. Presently, the physical protection convention applies only to nuclear materials that are in international transport. To complement efforts to develop and promote international physical protection standards, the IAEA is actively involved in assisting member states with the implementation of the standards. This is accomplished through the delivery of training courses, workshops and hosting other international forums for the exchange of information. Through review services such as the international physical protection advisory service (IPPAS), the IAEA provides advice to member states on the application of international standards at national and facility-specific levels. These services can be followed up with technical support to implement the

International symposium on uranium production and raw materials for the nuclear fuel cycle - Supply and demand, economics, the environment and energy security. Extended synopses

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-07-01

The IAEA periodically organizes nical meetings and international symposia on all areas of the uranium production cycle. This publication contains 160 extended synopses related to the 2005 international symposium on 'Uranium Production and Raw Materials for the Nuclear Fuel Cycle - Supply and Demand, Economics, the Environment and Energy Security'. They cover all areas of natural uranium resources and production cycle including uranium supply and demand; uranium geology and deposit; uranium exploration; uranium mining and milling; waste management; and environment and regulation. Each synopsis was indexed individually.

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.)

Self-Supporting Nanoclay as Internal Scaffold Material for Direct Printing of Soft Hydrogel Composite Structures in Air.

Science.gov (United States)

Jin, Yifei; Liu, Chengcheng; Chai, Wenxuan; Compaan, Ashley; Huang, Yong

2017-05-24

Three dimensional (3D) bioprinting technology enables the freeform fabrication of complex constructs from various hydrogels and is receiving increasing attention in tissue engineering. The objective of this study is to develop a novel self-supporting direct hydrogel printing approach to extrude complex 3D hydrogel composite structures in air without the help of a support bath. Laponite, a member of the smectite mineral family, is investigated to serve as an internal scaffold material for the direct printing of hydrogel composite structures in air. In the proposed printing approach, due to its yield-stress property, Laponite nanoclay can be easily extruded through a nozzle as a liquid and self-supported after extrusion as a solid. Its unique crystal structure with positive and negative charges enables it to be mixed with many chemically and physically cross-linked hydrogels, which makes it an ideal internal scaffold material for the fabrication of various hydrogel structures. By mixing Laponite nanoclay with various hydrogel precursors, the hydrogel composites retain their self-supporting capacity and can be printed into 3D structures directly in air and retain their shapes before cross-linking. Then, the whole structures are solidified in situ by applying suitable cross-linking stimuli. The addition of Laponite nanoclay can effectively improve the mechanical and biological properties of hydrogel composites. Specifically, the addition of Laponite nanoclay results in a significant increase in the Young's modulus of each hydrogel-Laponite composite: 1.9-fold increase for the poly(ethylene glycol) diacrylate (PEGDA)-Laponite composite, 7.4-fold increase for the alginate-Laponite composite, and 3.3-fold increase for the gelatin-Laponite composite.

International projects of the Chair for waste and material flow management in the period 2010-2014

International Nuclear Information System (INIS)

Nelles, Michael

2015-01-01

The waste and material flow management must align progressively to the requirements of sustainable resource and climate protection targets. She has become a recycling economy. One of the key global challenges of the future is to ensure a sustainable, i.e. economically, environmentally and socially sustainable supply of raw materials and energy. In both areas, the recycling economy make an important contribution. For Germany, despite of the ambitious targets, a positive balance can be drawn. In particular, the positive environmental effects of prevention, recovery and disposal of waste are supported by numerous scientific studies. While the recycling economy has performed well in Germany, many countries in the world are still in the beginning of a sustainable waste management development. Our Chair for Waste and Material Flow Management at the Faculty of Agricultural and Environmental Sciences of the University of Rostock has been involved for over 15 years in international technology and knowledge transfer. The regional focus are the Arab and Asian region (esp. China) and for some years, the Baltic countries, Eastern Europe and South America. Often in the projects stand in the foreground, to inform key decision-makers on the state of technology and to work out possible administrative solutions and customized technical solutions together and implement. In addition, classic R and D projects in these regions have been processed. In the framework of student works, studies in other countries, amongst other things in Vietnam and Chile, are carried out. [de

Classical entropy generation analysis in cooled homogenous and functionally graded material slabs with variation of internal heat generation with temperature, and convective–radiative boundary conditions

International Nuclear Information System (INIS)

Torabi, Mohsen; Zhang, Kaili

2014-01-01

This article investigates the classical entropy generation in cooled slabs. Two types of materials are assumed for the slab: homogeneous material and FGM (functionally graded material). For the homogeneous material, the thermal conductivity is assumed to be a linear function of temperature, while for the FGM slab the thermal conductivity is modeled to vary in accordance with the rule of mixtures. The boundary conditions are assumed to be convective and radiative concurrently, and the internal heat generation of the slab is a linear function of temperature. Using the DTM (differential transformation method) and resultant temperature fields from the DTM, the local and total entropy generation rates within slabs are derived. The effects of physically applicable parameters such as the thermal conductivity parameter for the homogenous slab, β, the thermal conductivity parameter for the FGM slab, γ, gradient index, j, internal heat generation parameter, Q, Biot number at the right side, Nc 2 , conduction–radiation parameter, Nr 2 , dimensionless convection sink temperature, δ, and dimensionless radiation sink temperature, η, on the local and total entropy generation rates are illustrated and explained. The results demonstrate that considering temperature- or coordinate-dependent thermal conductivity and radiation heat transfer at both sides of the slab have great effects on the entropy generation. - Highlights: • The paper investigates entropy generation in a slab due to heat generation and convective–radiative boundary conditions. • Both homogeneous material and FGM (functionally graded material) were considered. • The calculations are carried out using the differential transformation method which is a well-tested analytical technique

Can superabsorbent polymers mitigate shrinkage in cementitious materials blended with supplementary cementitious materials?

DEFF Research Database (Denmark)

Snoeck, Didier; Jensen, Ole Mejlhede; De Belie, Nele

2016-01-01

A promising way to mitigate autogenous shrinkage in cementitious materials with a low water-to-binder ratio is internal curing by the use of superabsorbent polymers. Superabsorbent polymers are able to absorb multiple times their weight in water and can be applied as an internal water reservoir...... to induce internal curing and mitigation of self-desiccation. Their purposefulness has been demonstrated in Portland cement pastes with and without silica fume. Nowadays, fly ash and blast-furnace slag containing binders are also frequently used in the construction industry. The results on autogenous...... shrinkage in materials blended with fly ash or blast-furnace slag remain scarce, especially after one week of age. This paper focuses on the autogenous shrinkage by performing manual and automated shrinkage measurements up to one month of age. Without superabsorbent polymers, autogenous shrinkage...

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

International Nuclear Information System (INIS)

2007-01-01

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

Radiation materials science. V. 7

International Nuclear Information System (INIS)

Zelenskij, V.F.

1990-01-01

This volume includes the papers of the international conference on radiation materials in Alushta, Ukraine in May 1990. The main topics are: basic research in radiation damage physics, a study of the structural materials for reactor cores; irradiation effect on reactor vessel, fuel, super- and semiconductor materials; investigation damage research methods

Radiation materials science. V. 6

International Nuclear Information System (INIS)

Zelenskij, V.F.

1990-01-01

This volume includes the papers of the international conference on radiation materials in Alushta, Ukraine in May 1990. The main topics are: basic research in radiation damage physics, a study of the structural materials for reactor cores; irradiation effect on reactor vessel, fuel, super- and semiconductor materials; investigation damage research methods

A Uniform Framework of Global Nuclear Materials Management

International Nuclear Information System (INIS)

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

1999-01-01

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

A Uniform Framework of Global Nuclear Materials Management

Energy Technology Data Exchange (ETDEWEB)

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

1999-04-20

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

Fusion Reactor Materials

International Nuclear Information System (INIS)

Decreton, M.

2002-01-01

The objective of SCK-CEN's programme on fusion reactor materials is to contribute to the knowledge on the radiation-induced behaviour of fusion reactor materials and components as well as to help the international community in building the scientific and technical basis needed for the construction of the future reactor. Ongoing projects include: the study of the mechanical and chemical (corrosion) behaviour of structural materials under neutron irradiation and water coolant environment; the investigation of the characteristics of irradiated first wall material such as beryllium; investigations on the management of materials resulting from the dismantling of fusion reactors including waste disposal. Progress and achievements in these areas in 2001 are discussed

International Research and Studies Program

Science.gov (United States)

Office of Postsecondary Education, US Department of Education, 2012

2012-01-01

The International Research and Studies Program supports surveys, studies, and instructional materials development to improve and strengthen instruction in modern foreign languages, area studies, and other international fields. The purpose of the program is to improve and strengthen instruction in modern foreign languages, area studies and other…

Research of plating aluminum and aluminum foil on internal surface of carbon fiber composite material centrifuge rotor drum

International Nuclear Information System (INIS)

Lu Xiuqi; Dong Jinping; Dai Xingjian

2014-01-01

In order to improve the corrosion resistance, thermal conductivity and sealability of the internal surface of carbon fiber/epoxy composite material centrifuge rotor drum, magnetron sputtering aluminum and pasting an aluminum foil on the inner wall of the drum are adopted to realize the aim. By means of XRD, SEM/EDS and OM, the surface topography of aluminum coated (thickness of 5 μm and 12 μm) and aluminum foil (12 μm) are observed and analyzed; the cohesion of between aluminum coated (or aluminum foil) and substrate material (CFRP) is measured by scratching experiment, direct drawing experiment, and shear test. Besides, the ultra-high-speed rotation experiment of CFRP ring is carried out to analyze stress and strain of coated aluminum (or aluminum foil) which is adhered on the ring. The results showed aluminum foil pasted on inner surface do better performance than magnetron sputtering aluminum on CFRP centrifuge rotor drum. (authors)

Thermonuclear controlled fusion: international cooperation

International Nuclear Information System (INIS)

Conscience, J.-F.

2001-01-01

This report summarizes the current worldwide status of research in the field of thermonuclear controlled fusion as well as the international research programme planed for the next decades. The two main projects will be the ITER facility (International Thermonuclear Experimental Reactor) that should produce 10 times more energy than the energy injected, and the IFMIF (International Fusion Materials Irradiation Facility) designed to study the reactions of materials under intense neutron fluxes. The future of the pioneering JET facility (Joint European Torus) is also discussed. The engagement of the various countries (USA, Japan, Germany, Russian Federation and Canada) and international organisations (EURATOM and IEA) in terms of investment and research is described. Switzerland is involved in this program through an agreement with EURATOM and is mainly dedicated to experimental studies with the TCV machine in Lausanne and numerical studies of plasma configurations. It will participate to the development of the microwave plasma heating system for the ITER machine

On possibility of degradation of lava-like fuel-containing materials of the 4-th block of Chernobyl NPP under internal self-irradiation by alpha-particle sources

International Nuclear Information System (INIS)

Pazukhin, Eh. M.; Borovoj, A.A.; Rudya, K.G.

2002-01-01

It is shown that internal self-irradiation by alpha-particle beam cannot be a cause of change of strength characteristics of silicate matrix and so a cause of degradation of Chernobyl lava-like materials. A new method is proposed for management with lava-like fuel-containing materials of the 4-th block: vitrification in smelter unit situated in bubbler-basin and storage of prepared immobilized compacts in corresponding depositories [ru

Uncontrolled transport of nuclear materials

International Nuclear Information System (INIS)

Wassermann, U.

1985-01-01

An account is given of international transport of plutonium, uranium oxides, uranium hexafluoride, enriched uranium and irradiated fuel for reprocessing. Referring to the sinking of the 'Mont Louis', it is stated that the International Maritime Organization has been asked by the National Union of Seamen and 'Greenpeace' to bar shipment of radioactive material until stricter international safety regulations are introduced. (U.K.)

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

International research cooperation in fiscal 1997. Report on the results of researches for the development of tribo-materials; 1997 nendo kokusai kenkyu kyoryoku jigyo. Tribo material no kaihatsu chosa seika hokokusho

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-03-01

Researches were conducted for the development of tribo-materials for the improvement of energy efficiency for equipment with slide members usable for example aboard automobiles, and the result is reported for fiscal 1997. In the research for the creation of substrate materials, some metals different in hardness, iron-base materials, titanium-base materials, etc., were selected, and experiments were conducted to disclose the effect of the substrate hardness/surface roughness on the critical load under which gas phase coatings fracture. In the research about surface treatment, the arc ion plating method is employed to produce TiN coatings on substrates of SKD11 and Ti-6Al-4V, and the critical loads were evaluated using a heavy duty, acoustic detection type adhesion evaluator and a sliding wear tester. Furthermore, the substrate/coating interface is subjected to observation under high-resolution transmission electron microscope. As for the evaluation of coating characteristics, the effects of the hardness of the coating itself, Young`s modulus, and toughness on the fracture of the coating were investigated. During the international joint researches, information was exchanged with National Institute for Standards and Technology, U.S. 11 refs., 64 figs., 4 tabs.

Diagnosis, injury and prevention of internal radiation exposure

International Nuclear Information System (INIS)

Tatsuzaki, Hideo

2012-01-01

Radiation exposure is classified into three categories: external exposure, surface contamination, and internal exposure (also called internal contamination). Internal exposure is an exposure by the ionizing radiation emitted from radioactive materials taken into a human body. Uptake of radioactive materials can go through inhalation, ingestion, or wound contamination. Not like external exposure, alpha ray or beta ray, which has a limited penetration, is also important in internal exposure. Diagnosis of internal exposure is based on measurement and dose assessment in addition to the history taking. Two methods, direct measurement and/or bioassay (indirect measurement), are used for the measurement. These measurements provide information of radioactive materials in the body at the time of the measurement. The exposure dose to the body needs to be calculated in a process of dose assessment, based on the results of these measurements and history of intake, either acute intake or chronic intake. Another method, measurement of environmental samples or food stuff, is also used for dose assessment. For internal exposure, radiation dose to the body is expressed as committed effective dose or committed equivalent dose, which are accumulation of dose over a defined period. Radioactive materials taken into body are transferred among many body components depending on the type of radionuclide or chemicals etc. Some radioactive materials concentrate in a specific organ. Symptoms and signs depend on the distribution of the radioactive materials in the body. Monitoring the concentration in air or foods is conducted in order to control human activities and foods and consequently reduce the amount of intake to human bodies as a preventive measure. Prevention of internal exposure is also conducted by protective gears such as full face masks. Iodine prophylaxis could be used against radioactive iodine intake. Stable iodine, mostly potassium iodide, could be taken into the thyroid and

Protection and control of nuclear materials