Nuclear technology for the year 2000

International Nuclear Information System (INIS)

1987-01-01

Eighteen papers and abstracts are presented under the following session headings: space nuclear power, health physics and dosimetry, nuclear design and thermal hydraulics, nuclear diagnostics, and fusion technology and plasma physics. The papers were processed separately for the data base

Technology transfer from Canadian nuclear laboratories

International Nuclear Information System (INIS)

MacDonald, R.D.; Evans, W.; MacEwan, J.R.; Melvin, J.G.

1985-09-01

Canada has developed a unique nuclear power system, the CANDU reactor. AECL - Research Company (AECL-RC) has played a key role in the CANDU program by supplying its technology to the reactor's designers, constructors and operators. This technology was transferred from our laboratories to our sister AECL companies and to domestic industries and utilities. As CANDUs were built overseas, AECL-RC made its technology available to foreign utilities and agencies. Recently the company has embarked on a new transfer program, commercial R and D for nuclear and non-nuclear customers. During the years of CANDU development, AECL-RC has acquired the skills and technology that are especially valuable to other countries embarking on their own nuclear programs. This report describes AECL-RC's thirty years' experience with the transfer of technology

China general nuclear power corporation--The recent research and application of the modular technology in nuclear power engineering

International Nuclear Information System (INIS)

Lu Qinwu

2014-01-01

Modular design and construction is one of the distinctive features of the 3"r"d generation nuclear power technology. In order to promote the technological innovations in nuclear power engineering design and construction and develop the self-owned modular technology, China General Nuclear Power Corporation (CGN) has carried out the R and D and application of the modular technology based on the CPR1000-type nuclear power plants, and has made the national-level achievements in the establishment of modular design technology system, development of 3D modular design system and application of modular construction of containment steel liner in the demonstration projects. (author)

Siemens technology transfer and cooperation in the nuclear fuel area

International Nuclear Information System (INIS)

Holley, H.-P.; Fuchs, J. H.; Rothenbuecher, R. A.

1997-01-01

Siemens is a full-range supplier in the area of nuclear power generation with broad experience and activities in the field of nuclear fuel. Siemens has developed advanced fuel technology for all types fuel assemblies used throughout the world and has significant experience worldwide in technology transfer in the field of nuclear fuel. Technology transfer and cooperation has ranged between the provision of mechanical design advice for a specific fuel design and the erection of complete fabrication plants for commercial operation in 3 countries. In the following the wide range of Siemens' technology transfer activities for both fuel design and fuel fabrication technologies are shown

Canada's commitment to nuclear technology

International Nuclear Information System (INIS)

Stewart, Murray J.

1998-01-01

This paper gives a broad update on all facets of the Canadian nuclear industry and demonstrates Canada's continuing commitment to nuclear technology. Canada has developed a global leadership position in nuclear technology for power generation, uranium production and isotope supply. This commitment is being further enhanced by successes in international markets with Candu technology, new uranium mine developments in our province of Saskatchewan, and expanding isotope capabilities including the construction of two new production reactors. Korea's economy is benefiting through collaboration with Canada's leading nuclear companies, both in Korea and Canada. These collaborations have the potential to expand considerably with the implementation of the Kyoto Framework Convention on Climate Change and the anticipated increased demand for new nuclear power generation installations in all major global markets. Much has been publicized about the situation surrounding Ontario Hydro Nuclear and its nuclear recovery program. This paper gives the background and highlights the actions within Ontario and Ontario Hydro designed to ensure the long term recovery of all twenty nuclear units in Ontario. The presentation at the conference will bring the audience completely up-to-date on recent events. (author)

Information Technology for Nuclear Power Plant Configuration Management

International Nuclear Information System (INIS)

2010-07-01

Configuration management (CM) is an essential component of nuclear power plant design, construction and operation. The application of information technology (IT) offers a method to automate and ensure the timely and effective capture, processing and distribution of key nuclear power plant information to support CM principles and practical processes and procedures for implementation of CM at nuclear power plants. This publication reviews some of the principles established in IAEA-TECDOC-1335, 'Configuration Management in Nuclear Power Plants.' It also recaps tenets laid out in IAEA- TECDOC-1284, 'Information Technology Impact on Nuclear Power Plant Documentation' that supports CM programmes. This publication has been developed in conjunction with and designed to support these other two publications. These three publications combined provide a comprehensive discussion on configuration management, information technology and the relationship between them. An extensive discussion is also provided in this publication on the role of the design basis of the facility and its control through the CM process throughout the facility's lifetime. While this report was developed specifically for nuclear power plants, the principles discussed can be usefully applied to any high hazard nuclear facility

Design and implementation of the system of importing data of nuclear analysis experiment based on UML technology

International Nuclear Information System (INIS)

Peng Yanguang; Yu Chuansong; Ma Mei; Sun Gongxing

2004-01-01

There are some problems that Excel data importing to database for our scientific data processing, we introduce a method how to use UML and XML technology design and implementation our system. Because XML technology have flexible data exchange mechanism, so it is appropriate to do it, and it is easy for use that the system of importing data of nuclear analysis experiment has a web browser GUI. Our paper emphasis on the software design method and UML design cases. (authors)

Development of System Engineering Technology for Nuclear Fuel Cycle

International Nuclear Information System (INIS)

Kim, Ho Dong; Kim, Sung Ki; Song, Kee Chan

2010-04-01

This report is aims to establish design requirements for constructing mock-up system of pyroprocess by 2011 to realize long-term goal of nuclear energy promotion comprehensive plan, which is construction of engineering scale pyroprocess integrated process demonstration facility. The development of efficient process for spent fuel and establishment of system engineering technology to demonstrate the process are required to develop nuclear energy continuously. The detailed contents of research for these are as follows; - Design of Mock-up facility for demonstrate pyroprocess, Construction, Approval, Trial run, Performance test - Development of nuclear material accountancy technology for unit processes of pyroprocess and design of safeguards system - Remote operation of demonstrating pyroprocess / Development of maintenance technology and equipment - Establishment of transportation system and evaluation of pre-safety for interim storage system - Deriving and implementation of a method to improve nuclear transparency for commercialization proliferation resistance nuclear fuel cycle Spent fuel which is the most important pending problem of nuclear power development would be reduced and recycled by developing the system engineering technology of pyroprocess facility by 2010. This technology would contribute to obtain JD for the use of spent fuel between the ROK-US and to amend the ROK-US Atomic Energy Agreement scheduled in 2014

Study on international publicity and export strategy establishment of nuclear technology

Energy Technology Data Exchange (ETDEWEB)

Lee, Ji Bok; Choi, C.O.; Park, K. B.; Chang, M. H.; Kim, K. K.; Yang, M. S.; Jung, I. H.; Kim, K. P.; Wu, J. S.; Jang, C. I.; Han, B. O.; Sim, J. H.; Chung, M.; Chung, J.K

1999-05-01

The objective of this study is to devise a proper measure for international publicity and technology export strategy. Analysed and summaries in detail are other countries nuclear policy trend and the current technology development status of Korea Standard Nuclear Plant that we developed on our own technology, design and construction technology for research reactor, System-integrated Modular Advanced Reactor of which design is in progress, Direct use of Spent PWR Fuel in CANDU Reactors, and Radioisotopes. Based on that, the measures are proposed for the export industrialization of nuclear technology and establishment of the export basis. Also the international nuclear cooperation and publicity strategy are suggested to support the technology export basis. By surveying the world nuclear status, the direction for the international cooperation and publicity is settled and the specific publicity strategy is proposed for the cooperation with IAEA and multi-countries and the establishment of the nuclear technology export basis. As part of this project, the panel on major technologies such as Korea Standard Nuclear Plant, HANARO, and System-integrated Modular Advanced Reactor was displayed successfully at the IAEA meeting, which contribute much to the publicity of our nuclear technology to the international nuclear society. (author)

Application of radionuclides in nuclear technology

International Nuclear Information System (INIS)

Boeck, H.

1983-07-01

Four main applications of radionuclides in nuclear technology are presented which are level-, density- and thickness gauging and moisture determination. Each method is surveyed for its general principle, various designs, accuracy, errors and practical designs. (Author)

Study on modular technology based on the reference nuclear power plant

International Nuclear Information System (INIS)

Lu Qinwu; Zhao Shuyu; Li Yi; Han Xiaoping; Chai Weidong; Zhang Shuxia

2014-01-01

As an important technology for shortening the construction period and reducing the cost of nuclear power project, modular technology has become one of the development orientations of the third generation nuclear power plant. Taking CPR1000 nuclear power reactor as reference plant and drawing on advanced foreign technology of modularization, the overall concept design has been completed with the help of the self-developed 3D modular design system. On this basis, a typical detailed design work has been carried out so as to verify the feasibility of technology. Besides, an analysis on implementation of modular technology has been made from two aspects (procurement and construction), and the feasibility of research results in actual project has been evaluated. It provides references for the promotion of self-reliant modular technology in nuclear power project in China. (authors)

Nuclear technology in Canada

International Nuclear Information System (INIS)

1983-01-01

This pamphlet provides a summary of the research being carried out by Atomic Energy of Canada Limited. The design and development of the CANDU type reactor are highlighted and the contribution of nuclear technology to medicine, agriculture and the Canadian economy is briefly discussed

Design of compact nuclear power marine engineering simulator

International Nuclear Information System (INIS)

Gao Jinghui; Xing Hongchuan; Zhang Ronghua; Yang Yanhua; Xu Jijun

2004-01-01

The essentiality of compact nuclear power marine engineering simulator (NPMES) is discussed. The technology of nuclear power plant engineering simulator (NPPES) for NPMES development is introduced, and the function design, general design and model design are given in details. A compact NPMES based on the nuclear power marine of 'Mutsu' is developed. The design can help the development of NPMES, which will improve operation safety and management efficiency of marine. (authors)

Advances in nuclear science and technology

CERN Document Server

Henley, Ernest J

1970-01-01

Advances in Nuclear Science and Technology, Volume 5 presents the underlying principles and theory, as well as the practical applications of the advances in the nuclear field. This book reviews the specialized applications to such fields as space propulsion.Organized into six chapters, this volume begins with an overview of the design and objective of the Fast Flux Test Facility to provide fast flux irradiation testing facilities. This text then examines the problem in the design of nuclear reactors, which is the analysis of the spatial and temporal behavior of the neutron and temperature dist

Technology transfer of the systematic approach to training to Soviet designed nuclear power plants

International Nuclear Information System (INIS)

Haber, S.B.; Yoder, J.A.

1998-01-01

International Nuclear Safety Program initiated by US DOE in 1992 in Russia and Ukraine was expanded to include Armenia (together with IAEA), Bulgaria, Lithuania and Slovak Republic. Presentation describes the background, objectives, activities and key accomplishments of technology transfer of SAT to Soviet designed NPPs. High level of cooperation between countries was achieved showing mutual commitment of US and the countries involved to improve the quality of training of NPP personnel. Technology transfer will succeed because of the efforts and dedication of personnel from the initial sites in Russia and Ukraine

Design concepts of nuclear desalination plants

International Nuclear Information System (INIS)

2002-11-01

Interest in using nuclear energy for producing potable water has been growing worldwide in the past decade. This has been motivated by a variety of factors, including economic competitiveness of nuclear energy, the growing need for worldwide energy supply diversification, the need to conserve limited supplies of fossil fuels, protecting the environment from greenhouse gas emissions, and potentially advantageous spin-off effects of nuclear technology for industrial development. Various studies, and at least one demonstration project, have been considered by Member States with the aim of assessing the feasibility of using nuclear energy for desalination applications under specific conditions. In order to facilitate information exchange on the subject area, the IAEA has been active for a number of years in compiling related technical publications. In 1999, an inter regional technical co-operation project on Integrated Nuclear Power and desalination System Design was launched to facilitate international collaboration for the joint development by technology holders and potential end users of an integrated nuclear desalination system. This publication presents material on the current status of nuclear desalination activities and preliminary design concepts of nuclear desalination plants, as made available to the IAEA by various Member States. It is aimed at planners, designers and potential end-users in those Member States interested in further assessment of nuclear desalination. Interested readers are also referred to two related and recent IAEA publications, which contain useful information in this area: Introduction of Nuclear Desalination: A Guidebook, Technical Report Series No. 400 (2000) and Safety Aspects of Nuclear Plants Coupled with Seawater Desalination Units, IAEA-TECDOC-1235 (2001)

Operational safety enhancement of Soviet-designed nuclear reactors via development of nuclear power plant simulators and transfer of related technology

International Nuclear Information System (INIS)

Kohut, P.; Epel, L.G.; Tutu, N.K.

1998-01-01

The US Department of Energy (DOE), under the US government's International Nuclear Safety Program (INSP), is implementing a program of developing and providing simulators for many of the Russian and Ukrainian Nuclear Power Plants (NPPs). Pacific Northwest National Laboratory (PNNL) and Brookhaven National Laboratory (BNL) manage and provide technical oversight of the various INSP simulator projects for DOE. The program also includes a simulator technology transfer process to simulator design organizations in Russia and Ukraine. Training programs, installation of new simulators, and enhancements in existing simulators are viewed as providing a relatively fast and cost-effective technology transfer that will result in measurable improvement in the safety culture and operation of NPPs. A review of this program, its present status, and its accomplishments are provided in this paper

New technologies for lower-cost design and construction of new nuclear power plants. Annex 20

International Nuclear Information System (INIS)

Ritterbusch, S.E.; Bryan, R.E.; Harmon, D.L.

2002-01-01

Electric Power Research Institute studies indicate that in order to be competitive with gas-fired electric power plant capital costs, new nuclear plant capital cost in the USA must be decreased by at least 35% to 40% relative to costs of some Advanced Light Water Reactors designed in the early 1990s. To address this need, the U. S. Department of Energy is sponsoring three separate projects under its Nuclear Energy Research Initiative. These projects are the Risk-Informed Assessment of Regulatory and Design Requirements for Future Nuclear Power Plants, the Smart Equipment Nuclear Power Plant Program, and the Design, Procure, Construct, Install and Test Program. The goal of the Design-Construction program is reduction of the complete nuclear plant design-procure-construct-install-test cycle schedule and cost. A 3D plant model was combined with a construction schedule to produce a 4D visualization of plant construction, which was then used to analyze plant construction methods. Insights include the need for concurrent engineering, a plant-wide central database, and use of the World-Wide WEB. The goal of Smart Equipment program is to design, develop, and evaluate the methods for implementing smart equipment and predictive maintenance technology. 'Smart' equipment means components and systems that are instrumented and monitored to detect incipient failures in order to improve their reliability. The resulting smart equipment methods will be combined with a more risk-informed regulatory approach to allow plant designers to (1) simplify designs without compromising overall reliability and safety and (2) maintain more reliable plants at lower cost. Initial results show that rotating equipment such as charging pumps would benefit most from smart instrumentation and that the technique of Bayesian Belief Networks would be most appropriate for providing input to a health monitoring system. (author)

Innovation in nuclear energy technology

International Nuclear Information System (INIS)

Dujardin, Th.; Bertel, E.; Kwang Seok, Lee; Foskolos, K.

2007-01-01

Innovation has been a driving force for the success of nuclear energy and remains essential for its sustainable future. Many research and development programmes focus on enhancing the performance of power plants in operation, current fuel design and characteristics, and fuel cycle processes used in existing facilities. Generally performed under the leadership of the industry. Some innovation programmes focus on evolutionary reactors and fuel cycles, derived from systems of the current generation. Such programmes aim at achieving significant improvements, in the field of economics or resource management for example, in the medium term. Often, they are undertaken by the industry with some governmental support as they require basic research together with technological development and adaptation. Finally, large programmes, often undertaken in an international, intergovernmental framework are devoted to design and development of a new generation of systems meeting the goals of sustainable development in the long term. Driving forces for nuclear innovation vary depending on the target technology, the national framework and the international context surrounding the research programme. However, all driving factors can be grouped in three categories: market drivers, political drivers and technology drivers. Globally, innovation in the nuclear energy sector is a success story but is a lengthy process that requires careful planning and adequate funding to produce successful outcomes

Organizational factors in design and implementation of technological and organizational solutions in the nuclear industry

Energy Technology Data Exchange (ETDEWEB)

Macchi, L.; Reiman, T.; Savioja, P. (VTT Technical Research Centre of Finland (Finland)); Kahlbom, U. (Risk Pilot AB, Stockholm (Sweden)); Rollenhagen, C. (Vattenfall (Sweden))

2012-03-15

Design is often found as one of the contributing factors in accident in the nuclear industry. The design of new technological systems and organisational structures has to take into account and be driven by the future users' needs and has to consider how their role and work practices within the organisation will be affected. The SADE project explores to which extend the concepts of safety culture and resilience engineering can contribute to the prevention of design errors when no hindsight data are available. In 2011, the SADE project focused on gathering experience and clarifying the current issues and challenges related to the design process. During 2011 seventeen interviews have been conducted in Finland and Sweden to identify some of the major challenges the nuclear industry is currently facing. At the same time a literature review has been conducted to establish a sound common theoretical ground. This progress report presents some of the relevant theoretical findings and preliminary results from the interviews. (Author)

Organizational factors in design and implementation of technological and organizational solutions in the nuclear industry

International Nuclear Information System (INIS)

Macchi, L.; Reiman, T.; Savioja, P.; Kahlbom, U.; Rollenhagen, C.

2012-02-01

Design is often found as one of the contributing factors in accident in the nuclear industry. The design of new technological systems and organisational structures has to take into account and be driven by the future users' needs and has to consider how their role and work practices within the organisation will be affected. The SADE project explores to which extend the concepts of safety culture and resilience engineering can contribute to the prevention of design errors when no hindsight data are available. In 2011, the SADE project focused on gathering experience and clarifying the current issues and challenges related to the design process. During 2011 seventeen interviews have been conducted in Finland and Sweden to identify some of the major challenges the nuclear industry is currently facing. At the same time a literature review has been conducted to establish a sound common theoretical ground. This progress report presents some of the relevant theoretical findings and preliminary results from the interviews. (Author)

Review of Current Nuclear Vacuum System Technologies

International Nuclear Information System (INIS)

Carroll, M.; McCracken, J.; Shope, T.

2003-01-01

Nearly all industrial operations generate unwanted dust, particulate matter, and/or liquid wastes. Waste dust and particulates can be readily tracked to other work locations, and airborne particulates can be spread through ventilation systems to all locations within a building, and even vented outside the building - a serious concern for processes involving hazardous, radioactive, or nuclear materials. Several varieties of vacuum systems have been proposed and/or are commercially available for clean up of both solid and liquid hazardous and nuclear materials. A review of current technologies highlights both the advantages and disadvantages of the various systems, and demonstrates the need for a system designed to address issues specific to hazardous and nuclear material cleanup. A review of previous and current hazardous/nuclear material cleanup technologies is presented. From simple conventional vacuums modified for use in industrial operations, to systems specifically engineered for such purposes, the advantages and disadvantages are examined in light of the following criteria: minimal worker exposure; minimal secondary waste generation;reduced equipment maintenance and consumable parts; simplicity of design, yet fully compatible with all waste types; and ease of use. The work effort reviews past, existing and proposed technologies in light of such considerations. Accomplishments of selected systems are presented, including identified areas where technological improvements could be suggested

Effective Methods of Nuclear Power Technology Transfer

International Nuclear Information System (INIS)

Shave, D. F.; Kent, G. F.; Giambusso, A.

1987-01-01

An effective technology transfer program is a necessary and significant step towards independence in nuclear power technology. Attaining success in the conduct of such a program is a result of a) the donor and recipient jointly understanding the fundamental concepts of the learning process, b) sharing a mutual philosophy involving a partnership relationship, c) joint and careful planning, d) rigorous adherence to proven project management techniques, and e) presence of adequate feedback to assure continuing success as the program proceeds. Several years ago, KEPCO President Park, Jung-KI presented a paper on technology in which he stated, 'Nuclear technology is an integration of many unit disciplines, and thus requires extensive investment and training in order to establish the base for efficient absorption of transferred technology.' This paper addresses President Park's observations by discussing the philosophy, approach, and mechanisms that are necessary to support an efficient and effective process of nuclear power technology transfer. All technical content and presentation methods discussed are based on a technology transfer program developed by Stone and Webster, as an Engineer/Constructor for nuclear power plants, and are designed and implemented to promote the primary program goal - the ability of the trainees and the organization to perform specific nuclear power related multi-discipline function independently and competitively

Graduate diplomas in nuclear technology

Energy Technology Data Exchange (ETDEWEB)

Bereznai, G. [Univ. of Ontario Inst. of Tech., Oshawa, Ontario (Canada)

2009-07-01

The University of Ontario Institute of Technology (UOIT) offers a graduate diploma program in nuclear technology that consists of a suite of six sub-specialties: Fuel, Materials and Chemistry; Reactor Systems; Operation and Maintenance; Safety, Licensing and Regulatory Affairs; Health Physics; and Radiological Applications. Four courses selected from a list that covers the knowledge and skill set of each sub-specialty have to be completed in order to gain a graduate diploma in the specific area. The program is designed to accommodate the needs of people working in the nuclear industry to upgrade their knowledge and skills, to promote career advancement and to provide a framework for lifelong learning. (author)

Nuclear technology international 1987

International Nuclear Information System (INIS)

Geary, Neville

1987-01-01

A total of 59 articles cover a wide range of subjects within the scope of nuclear power generation. The first 13 are concerned with the design and construction of nuclear reactors - PWRs, AGRs, Magnox reactors, fast reactors. The final article in this section is on reactor decommissioning. The next 33 papers all concern services to the nuclear power industry. These include the supply of uranium, uranium enrichment, fuel fabrication, reprocessing, spent fuel storage, robotics and remote handling and radioactive waste disposal. The 13 articles in the safety and public acceptability section concern fears over the Chernobyl accident, safety aspects of nuclear power including risk assessment, fire protection, quality assurance, earthquake tolerance, non-proliferation of nuclear weapons and finally, general problems of balancing advances in nuclear technology and economic desirability against a lack of public confidence in the industry. All reactor and fuel types are represented. Most of the articles concern nuclear power in Europe or North America. All are indexed separately. (UK)

Indigenous technology development : seismic switch for nuclear reactors

International Nuclear Information System (INIS)

Varghese, Shiju; Shah, Jay; Limaye, P.K.; Soni, N.L; Patel, R.J.

2016-01-01

After Fukushima incident it has become a regulatory requirement to have automatic reactor trip on detection of earthquake beyond OBE level. Seismic Switches that meets the technical specifications required for nuclear reactor use were not available in the market. Hence, on Nuclear Power Corporation of India Ltd (NPCIL's) request, Refuelling Technology Division, BARC has developed Seismic Switches (electronic earthquake detectors) required for this application. Functionality of the system was successfully tested using a Shake Table. Two different designs of seismic switches have been developed. One is a microcontroller based system (digital) and the other is fully analogue electronics (analog) based. These switches are designed to meet the technical requirements of Class IA systems of nuclear reactors. It is also designed to meet other qualification tests such as EMI/EMC, climatic, vibration, and reliability requirements. In addition to nuclear industry seismic switches are having potential use in oil and gas, power plants, buildings and other industrial installations. These technologies are currently available for technology transfer and details are published in BARC website. This paper describes the requirements, principle of operation, and features and testing of the developed systems. (author)

AFRA Network for Education in Nuclear Science and Technology

International Nuclear Information System (INIS)

Hashim, O.N.; Wanjala, F.

2017-01-01

The Africa Regional Cooperative Agreement for Research Development and Training related to Science and Technology (AFRA) established the AFRA Network for Education in Nuclear Science and Technology (AFRA-NEST) in order to implement AFRA strategy on Human Resource Development (HRD) and Nuclear Knowledge Management (NKM). The strategies for implementing the objectives are: to use ICT for web-based education and training; recognition of Regional Designated Centres (RDCs) for professional nuclear education in nuclear science and technology, and organization of harmonized and accredited programs at tertiary levels and awarding of fellowships/scholarships to young and brilliant students for teaching and research in the various nuclear disciplines

International nuclear technology transfer

International Nuclear Information System (INIS)

Cartwright, P.; Rocchio, J.P.

1978-01-01

Light water reactors (LWRs), originally developed in the United States, became the nuclear workhorses for utilities in Europe and Japan largely because the U.S. industry was willing and able to transfer its nuclear know-how abroad. In this international effort, the industry had the encouragement and support of the U.S. governement. In the case of the boiling water reactor (BWR) the program for technology transfer was developed in response to overseas customer demands for support in building local designs and manufacturing capabilities. The principal vehicles have been technology exchange agreements through which complete engineering and manufacturing information is furnished covering BWR systems and fuel. Agreements are held with companies in Germany, Japan, Italy, and Sweden. In recent years, a comprehensive program of joint technology development with overseas manufacturers has begun. The rapidly escalating cost of nuclear research and development make it desirable to minimize duplication of effort. These joint programs provide a mechanism for two or more parties jointly to plan a development program, assign work tasks among themselves, and exchange test results. Despite a slower-than-hoped-for start, nuclear power today is playing a significant role in the economic growth of some developing countries, and can continue to do so. Roughly half of the 23 free world nations that have adopted LWRs are developing countries

The role of computer simulation in nuclear technologies development

International Nuclear Information System (INIS)

Tikhonchev, M.Yu.; Shimansky, G.A.; Lebedeva, E.E.; Lichadeev, V. V.; Ryazanov, D.K.; Tellin, A.I.

2001-01-01

In the report the role and purposes of computer simulation in nuclear technologies development is discussed. The authors consider such applications of computer simulation as nuclear safety researches, optimization of technical and economic parameters of acting nuclear plant, planning and support of reactor experiments, research and design new devices and technologies, design and development of 'simulators' for operating personnel training. Among marked applications the following aspects of computer simulation are discussed in the report: neutron-physical, thermal and hydrodynamics models, simulation of isotope structure change and damage dose accumulation for materials under irradiation, simulation of reactor control structures. (authors)

Prospective of the nuclear energy, technological tendency

International Nuclear Information System (INIS)

Cruz F, G. De la; Salaices A, M.

2004-01-01

The world's concern about the energy supply in the near future, has had as an answer diverse proposals in which two multinational initiatives are highlighted, that of the International Project on Nuclear Innovative Reactors and Fuel Cycles (INPRO) and that of the Generation-l V International Forum (GIF). Both initiatives direct their efforts to the development of new technologies in nuclear energy that would satisfy the energy requirements of the future. In this article, an analysis based on a) the available information on these technologies, b) a joint study (IEA/OECD/IAEA) on the new technologies regarding its capacity to confront the current challenges of the nuclear energy, and c) the authors' experience and knowledge about the phenomenology, design and security of nuclear facilities, is presented. Moreover, the technologies that, in the authors' opinion, will have the better possibilities to compete successfully in the energy markets and could be one of the viable options to satisfy the energy demands of the future, are described. (Author)

New nuclear plant design and licensing process

International Nuclear Information System (INIS)

Luangdilok, W.

1996-01-01

This paper describes latest developments in the nuclear power reactor technology with emphasis on three areas: (1) the US technology of advanced passive light water reactors (AP600 and S BWR), (2) regulatory processes that certify their safety, and (3) current engineering concerns. The goal is to provide and insight of how the government's regulatory agency guarantees public safety by looking into how new passive safety features were designed and tested by vendors and how they were re-evaluated and retested by the US NRC. The paper then discusses the US 1989 nuclear licensing reform (10 CFR Part 52) whose objectives are to promote the standardization of nuclear power plants and provide for the early and definitive resolution of site and design issues before plants are built. The new licensing process avoids the unpredictability nd escalated construction cost under the old licensing process. Finally, the paper summarizes engineering concerns found in current light water reactors that may not go away in the new design. The concerns are related the material and water chemistry technology in dealing with corrosion problems in water-cooled nuclear reactor systems (PWRs and BWRs). These engineering concerns include core shroud cracking (BWRs), jet pump hold-down beam cracking (BWRs), steam generator tube stress corrosion cracking (PWR)

Maintaining a Technology-Neutral Approach to Hydrogen Production Process Development through Conceptual Design of the Next Generation Nuclear Plant

International Nuclear Information System (INIS)

Michael W. Patterson

2008-01-01

The Next Generation Nuclear Plant (NGNP) project was authorized in the Energy Policy Act of 2005 (EPAct), tasking the U.S. Department of Energy (DOE) with demonstrating High Temperature Gas-Cooled Reactor (HTGR) technology. The demonstration is to include the technical, licensing, operational, and commercial viability of HTGR technology for the production of electricity and hydrogen. The Nuclear Hydrogen Initiative (NHI), a component of the DOE Hydrogen Program managed by the Office of Nuclear Energy, is also investigating multiple approaches to cost effective hydrogen production from nuclear energy. The objective of NHI is development of the technology and information basis for a future decision on commercial viability. The initiatives are clearly intertwined. While the objectives of NGNP and NHI are generally consistent, NGNP has progressed to the project definition phase and the project plan has matured. Multiple process applications for the NGNP require process heat, electricity and hydrogen in varied combinations and sizes. Coupling these processes to the reactor in multiple configurations adds complexity to the design, licensing and demonstration of both the reactor and the hydrogen production process. Commercial viability of hydrogen production may depend on the specific application and heat transport configuration. A component test facility (CTF) is planned by the NGNP to support testing and demonstration of NGNP systems, including those for hydrogen production, in multiple configurations. Engineering-scale demonstrations in the CTF are expected to start in 2012 to support scheduled design and licensing activities leading to subsequent construction and operation. Engineering-scale demonstrations planned by NHI are expected to start at least two years later. Reconciliation of these schedules is recommended to successfully complete both initiatives. Hence, closer and earlier integration of hydrogen process development and heat transport systems is sensible

Advanced digital technology - improving nuclear power plant performance through maintainability

International Nuclear Information System (INIS)

Ford, J.L.; Senechal, R.R.; Altenhein, G.D.; Harvey, R.P.

1998-01-01

In today's energy sector there is ever increasing pressure on utilities to operate power plants at high capacity factors. To ensure nuclear power is competitive into the next century, it is imperative that strategic design improvements be made to enhance the performance of nuclear power plants. There are a number of factors that affect a nuclear power plant's performance; lifetime maintenance is one of the major contributors. The maturing of digital technology has afforded ABB the opportunity to make significant design improvements in the area of maintainability. In keeping with ABB's evolutionary advanced nuclear plant design approach, digital technology has systematically been incorporated into the control and protection systems of the most recent Korean nuclear units in operation and under construction. One example of this was the multi-functional design team approach that was utilized for the development of ABB's Digital Plant Protection System (DPPS). The design team consisted of engineers, maintenance technicians, procurement specialists and manufacturing personnel in order to provide a complete perspective on all facets of the design. The governing design goals of increased reliability and safety, simplicity of design, use of off-the-shelf products and reduced need for periodic surveillance testing were met with the selection of proven ABB-Advant Programmable Logic Controllers (PLCs) as the heart of the DPPS. The application of digital PLC technology allows operation for extended periods without requiring routine maintenance or re-calibration. A well documented commercial dedication program approved by the United States Nuclear Regulatory Commission (US NRC) as part of the System 80+ TM Advanced Light Water Reactor Design Certification Program, allowed the use of off-the shelf products in the design of the safety protection system. In addition, a number of mechanical and electrical improvements were made which support maintainability. The result is a DPPS

Advanced nuclear energy analysis technology

International Nuclear Information System (INIS)

Gauntt, Randall O.; Murata, Kenneth K.; Romero, Vicente Josce; Young, Michael Francis; Rochau, Gary Eugene

2004-01-01

A two-year effort focused on applying ASCI technology developed for the analysis of weapons systems to the state-of-the-art accident analysis of a nuclear reactor system was proposed. The Sandia SIERRA parallel computing platform for ASCI codes includes high-fidelity thermal, fluids, and structural codes whose coupling through SIERRA can be specifically tailored to the particular problem at hand to analyze complex multiphysics problems. Presently, however, the suite lacks several physics modules unique to the analysis of nuclear reactors. The NRC MELCOR code, not presently part of SIERRA, was developed to analyze severe accidents in present-technology reactor systems. We attempted to: (1) evaluate the SIERRA code suite for its current applicability to the analysis of next generation nuclear reactors, and the feasibility of implementing MELCOR models into the SIERRA suite, (2) examine the possibility of augmenting ASCI codes or alternatives by coupling to the MELCOR code, or portions thereof, to address physics particular to nuclear reactor issues, especially those facing next generation reactor designs, and (3) apply the coupled code set to a demonstration problem involving a nuclear reactor system. We were successful in completing the first two in sufficient detail to determine that an extensive demonstration problem was not feasible at this time. In the future, completion of this research would demonstrate the feasibility of performing high fidelity and rapid analyses of safety and design issues needed to support the development of next generation power reactor systems

Nuclear technology and societal needs

International Nuclear Information System (INIS)

2004-11-01

This volume aims to review the present status of development of nuclear technologies and their applications in the country and also to make projections for future requirements. This will also cover state-of-the-art technologies in these areas. The following topics are covered in detail: nuclear technologies for water desalination, water resources development and management using nuclear technology, industrial applications of isotopes and radiation technology, radiation technology in health care, nuclear technology for food preservation, agricultural applications of nuclear technology. Papers relevant to INIS are indexed separately

Building tomorrow's nuclear power plants with 4+D VR technology

International Nuclear Information System (INIS)

Lee, Il S.; Yoon, Sang H.; Shim, Kyu W.; Yu, Yong H.; Suh, Kune Y.

2002-01-01

There continues to be an increasing demand of electricity around the globe to fuel the industrial growth and to promote the human welfare. The economic activities have brought about richness in our material and cultural lives, in which process the electric power has been at the heart of the versatile energy sources. In order to timely and competitively respond to rapidly changing energy environment in the twenty-first century there is a growing need to build the advanced nuclear power plants in the unlimited workspace of virtual reality (VR) prior to commissioning. One can then realistically evaluate their construction time and cost per varying methods and options available from the leading-edge technology. In particular a great deal of efforts have yet to be made for time- and cost-dependent plant simulation and dynamically coupled database construction in the VR space. The operator training and personnel education may also benefit from the VR technology. The present work is being proposed in the three-dimensional space and time plus cost coordinates, i. e. four plus dimensional (4 + D) coordinates. The 4 + D VR application will enable the nuclear industry to narrow the technological gap from the other leading industries that have long since been employing the VR engineering. The 4 + D technology will help nurture public understanding of the special discipline of nuclear power plants. The technology will also facilitate public access to the knowledge on the nuclear science and engineering which has so far been monopolized by the academia, national laboratories and the heavy industry. The 4 + D virtual design and construction will open up the new horizon for revitalization of the nuclear industry over the globe in the foreseeable future. Considering the long construction and operation time for the nuclear power plants, the preliminary VR simulation capability for the plants will supply the vital information not only for the actual design and construction of the

The role of computer simulation in nuclear technology development

International Nuclear Information System (INIS)

Tikhonchev, M.Yu.; Shimansky, G.A.; Lebedeva, E.E.; Lichadeev, VV.; Ryazanov, D.K.; Tellin, A.I.

2000-01-01

In the report, the role and purpose of computer simulation in nuclear technology development is discussed. The authors consider such applications of computer simulation as: (a) Nuclear safety research; (b) Optimization of technical and economic parameters of acting nuclear plant; (c) Planning and support of reactor experiments; (d) Research and design new devices and technologies; (f) Design and development of 'simulators' for operating personnel training. Among marked applications, the following aspects of computer simulation are discussed in the report: (g) Neutron-physical, thermal and hydrodynamics models; (h) Simulation of isotope structure change and dam- age dose accumulation for materials under irradiation; (i) Simulation of reactor control structures. (authors)

Nuclear power reactor technology

International Nuclear Information System (INIS)

1978-09-01

Risoe National Laboratory was established more than twenty years ago with research and development of nuclear reactor technology as its main objective. The Laboratory has by now accumulated many years of experience in a number of areas vital to nuclear reactor technology. The work and experience of, and services offered by the Laboratory within the following fields are described: Health physics site supervision; Treatment of low and medium level radioactive waste; Core performance evaluation; Transient analysis; Accident analysis; Fuel management; Fuel element design, fabrication and performance evaluation; Non-destructive testing of nuclear fuel; Theoretical and experimental structural analysis; Reliability analysis; Site evaluation. Environmental risk and hazard calculation; Review and analysis of safety documentation. Risoe has already given much assistance to the authorities, utilities and industries in such fields, carrying out work on both light and heavy water reactors. The Laboratory now offers its services to others as a consultant, in education and training of staff, in planning, in qualitative and quantitative analysis, and for the development and specification of fabrication techniques. (author)

Transfer of infrared thermography predictive maintenance technologies to Soviet-designed nuclear power plants: experience at Chernobyl

Science.gov (United States)

Pugh, Ray; Huff, Roy

1999-03-01

The importance of infrared (IR) technology and analysis in today's world of predictive maintenance and reliability- centered maintenance cannot be understated. The use of infrared is especially important in facilities that are required to maintain a high degree of equipment reliability because of plant or public safety concerns. As with all maintenance tools, particularly those used in predictive maintenance approaches, training plays a key role in their effectiveness and the benefit gained from their use. This paper details an effort to transfer IR technology to Soviet- designed nuclear power plants in Russia, Ukraine, and Lithuania. Delivery of this technology and post-delivery training activities have been completed recently at the Chornobyl nuclear power plant in Ukraine. Many interesting challenges were encountered during this effort. Hardware procurement and delivery of IR technology to a sensitive country were complicated by United States regulations. Freight and shipping infrastructure and host-country customs policies complicated hardware transport. Training activities were complicated by special hardware, software and training material translation needs, limited communication opportunities, and site logistical concerns. These challenges and others encountered while supplying the Chornobyl plant with state-of-the-art IR technology are described in this paper.

The international nuclear technology

International Nuclear Information System (INIS)

Remick, F.J.

1992-01-01

With today's technology, isolationism is virtually impossible. The world's economies are so strongly intertwined that what affects one country will, in some way, influence another. Nuclear technology is no exception. If anything, nuclear technology is a catalyst for international cooperation. In the United States of America, nuclear technology is undergoing significant changes. Many of these changes are being greatly influenced by programs of international cooperation

Design of an organic simplified nuclear reactor

Energy Technology Data Exchange (ETDEWEB)

Shirvan, Koroush [Dept. of Nuclear Science and Engineering, Massachusetts Institute of Technology, Cambridge (United States); Forrest, Eric [Primary Standards Laboratory, Sandia National Laboratories, Albuquerque (United States)

2016-08-15

Numerous advanced reactor concepts have been proposed to replace light water reactors ever since their establishment as the dominant technology for nuclear energy production. While most designs seek to improve cost competitiveness and safety, the implausibility of doing so with affordable materials or existing nuclear fuel infrastructure reduces the possibility of near-term deployment, especially in developing countries. The organic nuclear concept, first explored in the 1950s, offers an attractive alternative to advanced reactor designs being considered. The advent of high temperature fluids, along with advances in hydrocracking and reforming technologies driven by the oil and gas industries, make the organic concept even more viable today. We present a simple, cost-effective, and safe small modular nuclear reactor for offshore underwater deployment. The core is moderated by graphite, zirconium hydride, and organic fluid while cooled by the organic fluid. The organic coolant enables operation near atmospheric pressure and use of plain carbon steel for the reactor tank and primary coolant piping system. The core is designed to mitigate the coolant degradation seen in early organic reactors. Overall, the design provides a power density of 40 kW/L, while reducing the reactor hull size by 40% compared with a pressurized water reactor while significantly reducing capital plant costs.

Design of an Organic Simplified Nuclear Reactor

Directory of Open Access Journals (Sweden)

Koroush Shirvan

2016-08-01

Full Text Available Numerous advanced reactor concepts have been proposed to replace light water reactors ever since their establishment as the dominant technology for nuclear energy production. While most designs seek to improve cost competitiveness and safety, the implausibility of doing so with affordable materials or existing nuclear fuel infrastructure reduces the possibility of near-term deployment, especially in developing countries. The organic nuclear concept, first explored in the 1950s, offers an attractive alternative to advanced reactor designs being considered. The advent of high temperature fluids, along with advances in hydrocracking and reforming technologies driven by the oil and gas industries, make the organic concept even more viable today. We present a simple, cost-effective, and safe small modular nuclear reactor for offshore underwater deployment. The core is moderated by graphite, zirconium hydride, and organic fluid while cooled by the organic fluid. The organic coolant enables operation near atmospheric pressure and use of plain carbon steel for the reactor tank and primary coolant piping system. The core is designed to mitigate the coolant degradation seen in early organic reactors. Overall, the design provides a power density of 40 kW/L, while reducing the reactor hull size by 40% compared with a pressurized water reactor while significantly reducing capital plant costs.

Virtual reality technology as a tool for human factors requirements evaluation in design of the nuclear reactors control desks

International Nuclear Information System (INIS)

Grecco, Claudio H.S.; Santos, Isaac J.A.L.; Mol, Antonio C.A.; Carvalho, Paulo V.R.; Silva, Antonio C.F.; Ferreira, Francisco J.O.; Dutra, Marco A.M.

2007-01-01

The Virtual Reality (VR) is an advanced computer interface technology that allows the user to internet or to explore a three-dimensional environment through the computer, as was part of the virtual world. This technology presents great applicability in the most diverse areas of the human knowledge. This paper presents a study on the use of the VR as tool for human factors requirements evaluation in design of the nuclear reactors control desks. Moreover, this paper presents a case study: a virtual model of the control desk, developed using virtual reality technology to be used in the human factors requirements evaluation. This case study was developed in the Virtual Reality Laboratory at IEN, and understands the stereo visualization of the Argonauta research nuclear reactor control desk for a static ergonomic evaluation using check-lists, in accordance to the standards and human factors nuclear international guides (IEC 1771, NUREG-0700). (author)

Virtual reality technology as a tool for human factors requirements evaluation in design of the nuclear reactors control desks

Energy Technology Data Exchange (ETDEWEB)

Grecco, Claudio H.S.; Santos, Isaac J.A.L.; Mol, Antonio C.A.; Carvalho, Paulo V.R.; Silva, Antonio C.F.; Ferreira, Francisco J.O.; Dutra, Marco A.M. [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)]. E-mail: grecco@ien.gov.br; luquetti@ien.gov.br; mol@ien.gov.br; paulov@ien.gov.br; tonico@ien.gov.br; fferreira@ien.gov.br; dutra@ien.gov.br

2007-07-01

The Virtual Reality (VR) is an advanced computer interface technology that allows the user to internet or to explore a three-dimensional environment through the computer, as was part of the virtual world. This technology presents great applicability in the most diverse areas of the human knowledge. This paper presents a study on the use of the VR as tool for human factors requirements evaluation in design of the nuclear reactors control desks. Moreover, this paper presents a case study: a virtual model of the control desk, developed using virtual reality technology to be used in the human factors requirements evaluation. This case study was developed in the Virtual Reality Laboratory at IEN, and understands the stereo visualization of the Argonauta research nuclear reactor control desk for a static ergonomic evaluation using check-lists, in accordance to the standards and human factors nuclear international guides (IEC 1771, NUREG-0700). (author)

Development of the advanced CANDU technology -Development of basic technology for HWR design

International Nuclear Information System (INIS)

Seok, Ho Cheon; Seok, Soo Dong; Lee, Sang Yong

1996-07-01

It is believed that it is easier for Korea to become self-reliant in PHWR technology than in PWR technology, mainly because of the lower design pressure and temperature and because of the simplicity, economy, flexibility of the fuel cycle in comparison with PWR systems. Even though one has no doubt about the safety and the economics of the PHWR's that are now being operated or constructed in Korea. It is necessary to develop the advanced design technology for even safer and more economical PHWR systems to overcome the ever growing international resistance to sharing of nuclear technology and to meet the even more stringent requirements for the future public acceptance of nuclear power. This study is to develop the more advance design technology compared to the existing one, especially in the field of reactor physics, safety systems and safety evaluation to realize the above requirements. 71 tabs., 147 figs., 143 refs. (Author)

Development of the advanced CANDU technology -Development of basic technology for HWR design-

Energy Technology Data Exchange (ETDEWEB)

Suk, Hoh Chun; Lee, Sang Yong; Suk, Soo Dong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1995-07-01

It is believed that it is easier for Korea to become self-reliant in PHWR technology than in PWR technology, mainly because of the lower design pressure and temperature and because of the simplicity, economy, flexibility of the fuel cycle in comparison with PWR systems. Even though one has no doubt about the safety and the economics of the PHWR`s that are now being operated or constructed in Korea, it is necessary to develop the advanced design technology for even safer and more economical PHWR systems to overcome the ever growing international resistance to sharing of nuclear technology and to meet the even more stringent requirements for the future public acceptance of nuclear power. This study is to develop the more advance design technology compared to the existing one, by performing in-depth studies especially in the field of reactor physics, safety systems and safety evaluation to realize the above requirements. 90 figs, 50 tabs, 38 refs. (Author).

Development of the advanced CANDU technology -Development of basic technology for HWR design-

International Nuclear Information System (INIS)

Suk, Hoh Chun; Lee, Sang Yong; Suk, Soo Dong

1995-07-01

It is believed that it is easier for Korea to become self-reliant in PHWR technology than in PWR technology, mainly because of the lower design pressure and temperature and because of the simplicity, economy, flexibility of the fuel cycle in comparison with PWR systems. Even though one has no doubt about the safety and the economics of the PHWR's that are now being operated or constructed in Korea, it is necessary to develop the advanced design technology for even safer and more economical PHWR systems to overcome the ever growing international resistance to sharing of nuclear technology and to meet the even more stringent requirements for the future public acceptance of nuclear power. This study is to develop the more advance design technology compared to the existing one, by performing in-depth studies especially in the field of reactor physics, safety systems and safety evaluation to realize the above requirements. 90 figs, 50 tabs, 38 refs. (Author)

New technologies for monitoring nuclear materials

International Nuclear Information System (INIS)

Moran, B.W.

1993-01-01

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

The role of advanced nuclear power technologies in developing countries: Criteria and design requirements

International Nuclear Information System (INIS)

1990-02-01

The document includes the papers presented at the following two technical committee meetings organized by the IAEA: Technical Committee Meeting and Workshop on Criteria for the Introduction of Advanced Nuclear Power Technologies for Specific Applications in Developing Countries, Vienna, 27-30 June 1988 (14 papers) and Technical Committee Meeting and Workshop on Design Requirements for the Application of Advanced Concepts in Developing Countries, Vienna, 6-9 December 1988 (16 papers). A separate abstract was prepared for each of these papers

Unlocking the atom : the Canadian book on nuclear technology

International Nuclear Information System (INIS)

Tammemagi, H.; Jackson, D.

2002-01-01

This book describes Canada's role in developing a world-class reactor, medical isotope and food irradiation systems and it's leading role in uranium mining. It gives an introduction to both natural and man-made radiation and covers the spectrum of nuclear technology that includes power reactors, nuclear safety, nuclear waste, medicine, uranium, fusion, industrial and research applications. The second chapter in this book introduces the reader to nuclear fission, the fission reactor, nuclear weapons and the Candu Nuclear Power Reactor. The third chapter familiarizes the reader with different types of natural and man-made radiations. The fourth chapter discusses the biological effects of radiation. Electricity and the different technologies to produce electrical power are the subject of chapter five. The Candu reactor and the various Candu designs and performance are discussed in some detail in chapter six. In chapter seven the authors discuss the different types of reactors that have been constructed worldwide. Nuclear safety and nuclear regulations are the subject of chapter eight. In chapter nine the authors discuss nuclear power and the environment. High-level nuclear waste and nuclear waste disposal are discussed in chapter ten. Diagnostic and therapeutic nuclear medicine is the subject of chapter eleven. The benefits of nuclear technology in industry and science are discussed in chapter twelve. Uranium mining and uranium as the nuclear fuel are discussed in chapter thirteen. Chapter fourteen discusses the future of fission with respect to advanced Candu fuel cycles and advanced Candu reactor designs. Chapter fifteen is a discussion of nuclear fusion and Canada's role in fusion research. Chapter sixteen discusses nuclear science and research and the role of the National nuclear laboratory and the universities

Nuclear technology is dead - long live nuclear technology

International Nuclear Information System (INIS)

Mayer, G.

1976-01-01

While a group of German scientists asked for a moratorium for nuclear power plants in the Heidelberg memorandum, lecturers at the Reaktortagung in Duesseldorf offered convincing arguments in favour of nuclear technology and for the necessity of safety. Almost 2,000 participants, about 200 of those from 26 different countries, listened to 235 individual lectures on the state of science and technology. Main topics were activities in reactor safety research carried out in industry and in various institutes. (orig./RW) [de

Dry refabrication technology development of spent nuclear fuel

International Nuclear Information System (INIS)

Park, Geun Il; Lee, J. W.; Song, K. C.

2012-04-01

Key technologies highly applicable to the development of advanced nuclear fuel cycle for the spent fuel recycling were developed using spent fuel and simulated spent fuel (SIMFUEL). In the frame work of dry process oxide products fabrication and the property characteristics of dry process products, hot cell experimental data for decladding, powdering and oxide product fabrication from low and high burnup spent fuel have been produced, basic technology for fabrication of spent fuel standard material has been developed, and remotely modulated welding equipment has been designed and fabricated. Also, fabrication technology of simulated dry process products was established and property models were developed based on reproducible property measurement data. In the development of head-end technology for dry refabrication of spent nuclear fuel and key technologies for volume reduction of head-end process waste which are essential in back-end fuel cycle field including pyro-processing, advanced head-end unit process technology development includes the establishment of experimental conditions for synthesis of porous fuel particles using a granulating furnace and for preparation of UO2 pellets, and fabrication and performance demonstration of engineering scale equipment for off-gas treatment of semi-volatile nuclides, and development of phosphate ceramic technology for immobilization of used filters. Radioactivation characterization and treatment equipment design of metal wastes from pretreatment process was conducted, and preliminary experiments of chlorination/electrorefining techniques for the treatment of hull wastes were performed. Based on the verification of the key technologies for head-end process via the hot-cell tests using spent nuclear fuel, pre-conceptual design for the head-end equipments was performed

Dry refabrication technology development of spent nuclear fuel

Energy Technology Data Exchange (ETDEWEB)

Park, Geun Il; Lee, J. W.; Song, K. C.; and others

2012-04-15

Key technologies highly applicable to the development of advanced nuclear fuel cycle for the spent fuel recycling were developed using spent fuel and simulated spent fuel (SIMFUEL). In the frame work of dry process oxide products fabrication and the property characteristics of dry process products, hot cell experimental data for decladding, powdering and oxide product fabrication from low and high burnup spent fuel have been produced, basic technology for fabrication of spent fuel standard material has been developed, and remotely modulated welding equipment has been designed and fabricated. Also, fabrication technology of simulated dry process products was established and property models were developed based on reproducible property measurement data. In the development of head-end technology for dry refabrication of spent nuclear fuel and key technologies for volume reduction of head-end process waste which are essential in back-end fuel cycle field including pyro-processing, advanced head-end unit process technology development includes the establishment of experimental conditions for synthesis of porous fuel particles using a granulating furnace and for preparation of UO2 pellets, and fabrication and performance demonstration of engineering scale equipment for off-gas treatment of semi-volatile nuclides, and development of phosphate ceramic technology for immobilization of used filters. Radioactivation characterization and treatment equipment design of metal wastes from pretreatment process was conducted, and preliminary experiments of chlorination/electrorefining techniques for the treatment of hull wastes were performed. Based on the verification of the key technologies for head-end process via the hot-cell tests using spent nuclear fuel, pre-conceptual design for the head-end equipments was performed.

Book of extended synopses. International symposium on advanced nuclear power systems. Design, technology, safety and strategies for their deployment

International Nuclear Information System (INIS)

1993-01-01

During the symposium the design, technology, safety and strategy for the development of advanced nuclear power systems were discussed. 20 papers were presented at the symposium. A separate abstract was prepared for each of these papers. Refs

Localization of nuclear power plant technology

International Nuclear Information System (INIS)

Stiteler, F.Z.; Rudek, T.G.

1998-01-01

-effective localization of nuclear power in Asia. Nuclear power is more capital intensive than most other power generation options. This results in the electricity cost to the end user being more influenced by the initial cost than fuel, and other operations and maintenance expenses. Because developing nations typically have lower wages, it's a natural conclusion to maximize local capabilities to drive the capital cost as low as possible. To facilitate localization, new approaches to expediting the formation of a credible nuclear technology infrastructure in these emerging commercial nuclear power nations is discussed. This paper will examine localization of nuclear technology as one of the most promising methods to make nuclear power more affordable to the emerging markets in Asia. Localization will allow for the utilization of lower cost, local labor in the design, manufacture and construction of new nuclear power plants. ABB's practical localization philosophy is discussed with reference to previous experience and future expectations. (author)

Nuclear technologies

International Nuclear Information System (INIS)

Toyama, Makoto; Hamasaki, Manabu; Kobayashi, Masahiko; Hoshide, Akihiko; Katayama, Kimio; Nozawa, H.; Karigome, Satoshi

2010-01-01

In recent days, energy security is becoming a major global concern and it has been recognized that a major reduction in greenhouse-gas emissions is required to combat climate change. Considerable expansion and new introduction of nuclear power generation are currently being planned and considered for the further in various parts of the world. Nuclear technologies of the latest 10 years in Japan were reviewed with their characteristics, advancement and future perspective. Steady efforts have been made to construct new nuclear power stations with computer-aided engineering system and modular and prefabricated structures, extend the interval of periodic inspections under the new inspection system that should improve both safety and reliability, implement advanced measures against aging and develop the next-generation light water reactors including a medium small reactor. Export of nuclear power plants has been promoted with international business alliance or cooperation. Activities to close nuclear fuel cycle to ensure sustainable nuclear energy utilization have been promoted. Decommissioning technologies for Tokai power station have been developed and accumulated know-how will be utilized in light water reactors. (T. Tanaka)

National Nuclear Technology Map Development

International Nuclear Information System (INIS)

Shin, J. I.; Lee, T. J.; Yoon, S. W.

2005-03-01

The objective of NuTRM is to prepare a plan of nuclear R and D and technological innovations which is very likely to make nuclear technology a promising power source for future national developments. The NuTRM finds out systematically the nuclear R and D vision and the high-value-added strategic technologies to be developed by the efficient cooperation of actors including government, industry, academy and research institute by 2020. In other words, NuTRM aims at a long-term strategic planning of nuclear R and D and technological innovation in order to promote the socio-economic contributions of nuclear science and technology for the nation's future competitiveness and sustainable development and to raise the global status of the Korean nuclear R and D and Industry

Nuclear energy technology: theory and practice of commercial nuclear power

International Nuclear Information System (INIS)

Knief, R.A.

1982-01-01

Reviews Nuclear Energy Technology: Theory and Practice of Commercial Nuclear Power by Ronald Allen Knief, whose contents include an overview of the basic concepts of reactors and the nuclear fuel cycle; the basics of nuclear physics; reactor theory; heat removal; economics; current concerns at the front and back ends of the fuel cycle; design descriptions of domestic and foreign reactor systems; reactor safety and safeguards; Three Mile Island; and a brief overview of the basic concepts of nuclear fusion. Both magnetic and inertial confinement techniques are clearly outlined. Also reviews Nuclear Fuel Management by Harry W. Graves, Jr., consisting of introductory subjects (e.g. front end of fuel cycle); core physics methodology required for fuel depletion calculations; power capability evaluation (analyzes physical parameters that limit potential core power density); and fuel management topics (economics, loading arrangements and core operation strategies)

Reexamining the Ethics of Nuclear Technology.

Science.gov (United States)

Andrianov, Andrei; Kanke, Victor; Kuptsov, Ilya; Murogov, Viktor

2015-08-01

This article analyzes the present status, development trends, and problems in the ethics of nuclear technology in light of a possible revision of its conceptual foundations. First, to better recognize the current state of nuclear technology ethics and related problems, this article focuses on presenting a picture of the evolution of the concepts and recent achievements related to technoethics, based on the ethics of responsibility. The term 'ethics of nuclear technology' describes a multidisciplinary endeavor to examine the problems associated with nuclear technology through ethical frameworks and paradigms. Second, to identify the reasons for the intensification of efforts to develop ethics in relation to nuclear technology, this article presents an analysis of the recent situation and future prospects of nuclear technology deployment. This includes contradictions that have aggravated nuclear dilemmas and debates stimulated by the shortcomings of nuclear technology, as well as the need for the further development of a nuclear culture paradigm that is able to provide a conceptual framework to overcome nuclear challenges. Third, efforts in the field of nuclear technology ethics are presented as a short overview of particular examples, and the major findings regarding obstacles to the development of nuclear technology ethics are also summarized. Finally, a potential methodological course is proposed to overcome inaction in this field; the proposed course provides for the further development of nuclear technology ethics, assuming the axiological multidisciplinary problematization of the main concepts in nuclear engineering through the basic ethical paradigms: analytical, hermeneutical, and poststructuralist.

Progress of research and development of nuclear fusion and development of large nuclear fusion device technology

International Nuclear Information System (INIS)

1994-01-01

In the last several years, the results of tokamak experiments were conspicuous, and the progress of plasma confinement performance, transport mechanism, divertors and impurities, helium transport and exhaust, electric current drive, magnetic field ripple effect and high speed particle transport and DT experiment are reported. The other confinement methods than tokamak, the related theories and reactor technology are described. The conceptual design of ITER was carried out by the cooperation of Japan, USA, EC and the former USSR. The projects of developing nuclear fusion in various countries, the design and the required research and development of ITER, the reconstruction and the required research and development of JT-60, JET and TFTR, the design and the required research and development of large helical device, the state of research and development of laser nuclear fusion and inversion magnetic field pinch nuclear fusion, the activities and roles of industrial circles in large nuclear fusion device technology, and the long term perspective of the technical development of nuclear fusion are described. (K.I.)

Non-nuclear power application of nuclear technology in Nigeria

International Nuclear Information System (INIS)

Funtua, I.I.

2008-01-01

Nuclear Technology applications are found in Food and Agriculture, Human Health, Water Resources, Industry, Environment, Education and Research.There are more potentials for the deployment of nuclear technology in more aspects of our life with needed economic development in Nigeria.Nuclear Technology plays and would continue to play vital role in Agriculture, Human health, Water resources and industry in Nigeria.Nuclear technologies have been useful in developmental efforts worldwide and for these to take hold, capacity building programmes must be expanded and the general public must have informed opinions about the benefits and risk associated with the technologies.This presentation gives an overview of nuclear technology applications in Nigeria in the following areas: Food and Agriculture, Human Health, Water Resources, Industry, Education and Research

Small Nuclear Technology and Market Entry

International Nuclear Information System (INIS)

Stewart, J S; Schock, R N; Brown, N W; Smith, C F

2002-01-01

An overview of energy-system projections into the new century leads to the conclusion that nuclear power will play a significant role. How significant a role will be determined by the marketplace. Within the range of nuclear-power technologies available, small nuclear-power plants of innovative design appear to fit the needs of a number of developing nations and states. Under similar financing options used by the airline industry and others, the capital requirement barrier that puts the nuclear industry at a disadvantage in deregulated markets could be reduced. These plants have the potential advantage of modularity, are proliferation-resistant, incorporate passive safety features, minimize waste, and could be cost-competitive with fossil-fuel plants

Nuclear power generation and automation technology

International Nuclear Information System (INIS)

Korei, Yoshiro

1985-01-01

The proportion of nuclear power in the total generated electric power has been increasing year after year, and the ensuring of its stable supply has been demanded. For the further development of nuclear power generation, the heightening of economical efficiency which is the largest merit of nuclear power and the public acceptance as a safe and stable electric power source are the important subjects. In order to solve these subjects, in nuclear power generation, various automation techniques have been applied for the purpose of the heightening of reliability, labor saving and the reduction of radiation exposure. Meeting the high needs of automation, the automation technology aided by computers have been applied to the design, manufacture and construction, operation and maintenance of nuclear power plants. Computer-aided design and the examples of design of a reactor building, pipings and a fuel assembly, an automatic welder for pipings of all position TIG welding type, a new central monitoring and control system, an automatic exchanger of control rod-driving mechanism, an automatic in-service inspection system for nozzles and pipings, and a robot for steam generator maintenance are shown. The trend of technical development and an intelligent moving robot, a system maintenance robot and a four legs walking robot are explained. (Kako, I.)

Current Status of Advanced Nuclear Fuel Cycle technologies

International Nuclear Information System (INIS)

Hwang, Yong Soo; Lee, Jong Hyun

2009-07-01

To expand the use of nuclear energy, SNF from nuclear power plants must be managed in a safe and environmental friendly and the problem of decreasing uranium should be solved. To resolve this, a dry processing technology Pyroprocessing is focused on. The government started to develop of Pyroprocessing technology in 1997. According to the decision of government based of Atomic Energy Commission in December 2008, the Korea Atomic Energy Research Institute will construct PRIDE (Pyroprocess Integrated Inactive DEmonstration Facility) by 2011 to prove a consistent process. If Pyroprocessing technology will be developed in the near future, the size of radioactive waste disposal site can be reduced to 100 times compared to the direct disposal. When this technology will be connected to Fast Reactor. high level nuclear waste management of Hundreds of thousands of years may be reduced to hundreds years. However for the commercialization of Pyroprocessing technology, there are some problems to solve. First, because of none commercial facilities in the world of executive experience, so that the facility design, measurement. management and material flow, the critical need for data accumulation. Second, High-level nuclear waste have been known to generate more than the wet methods, it should continue to reduce technology development. In addition, a careful consideration of the residual uranium generating on process also can maximize the efficiency of reducing. The new concept is being developed in Korea Atomic Energy Research Institute Pyroprocessing technology and nuclear waste processing technology to overcome these drawbacks sUQQested a way

Next Generation Nuclear Plant Pre-Conceptual Design Report

International Nuclear Information System (INIS)

Larry Demick; Doug Vandel

2007-01-01

management of the project using commercial processes, share the cost of design and construction with the government, and secure a commercial nuclear operating company to operate the plant. In FY-07, Pre-Conceptual Design (PCD) work was completed by the NGNP Project at the INL with the objective of developing a framework in which the design and technology development of the NGNP could progress and to begin to develop bases for selection of the specific design and operational characteristics of NGNP. This work was completed by three contractor teams with extensive experience in HTGR technology, nuclear power applications, and hydrogen production. The teams were led by Westinghouse Electric Company, LLC; AREVA NP, Inc.; and General Atomics. The scope of work included completion of special studies to address key aspects of the NGNP (e.g., reactor type, power levels, power conversion system [PCS] and heat transfer/transport system [HTS] designs, licensing and end product disposition). The results of these special studies were applied to the development by each contractor of a recommended design for NGNP and a commercial version of the HTGR. These were then used to estimate costs and schedule for design; construction; licensing; startup and testing; operation; and deactivation, decontamination, and decommissioning (DD and D) of the NGNP and an economic assessment for an Nth of a kind (NOAK) commercial plant. A primary objective of this work is to identify research and development (R and D), data needs, and future studies required to support selection of key characteristics of and to support the design and licensing processes for the NGNP. The Preliminary Project Management Plan (PPMP) for the NGNP identifies two planning options that weigh a range of programmatic risks and approaches to mitigating risk. The two options are compliant with the EPAct, but emphasize different approaches to technology development risks, design and construction risks, and the extent of demonstration in

Westinghouse Nuclear Core Design Training Center - a design simulator

International Nuclear Information System (INIS)

Altomare, S.; Pritchett, J.; Altman, D.

1992-01-01

The emergence of more powerful computing technology enables nuclear design calculations to be done on workstations. This shift to workstation usage has already had a profound effect in the training area. In 1991, the Westinghouse Electric Corporation's Commercial Nuclear Fuel Division (CNFD) developed and implemented a Nuclear Core Design Training Center (CDTC), a new concept in on-the-job training. The CDTC provides controlled on-the-job training in a structured classroom environment. It alllows one trainer, with the use of a specially prepared training facility, to provide full-scope, hands-on training to many trainees at one time. Also, the CDTC system reduces the overall cycle time required to complete the total training experience while also providing the flexibility of individual training in selected modules of interest. This paper provides descriptions of the CDTC and the respective experience gained in the application of this new concept

Technology Road-map - Nuclear Energy. 2015 edition

International Nuclear Information System (INIS)

Houssin, Didier; Dujardin, Thierry; Cameron, Ron; Tam, Cecilia; Paillere, Henri; Baroni, Marco; Bromhead, Amos; Baritaud, Manual; Cometto, Marco; Gaghen, Rebecca; Herzog, Antoine; Remme, Uwe; Urso, Maria-Elena; Vance, Robert

2015-01-01

-carbon electricity in OECD countries and second at global level. Nuclear can play a key role in lowering emissions from the power sector, while improving security of energy supply, supporting fuel diversity and providing large-scale electricity at stable production costs. In the 2D scenario, global installed capacity would need to more than double from current levels of 396 GW to reach 930 GW in 2050, with nuclear power representing 17% of global electricity production. The near-term outlook for nuclear energy has been impacted in many countries by the Fukushima Daiichi nuclear power plant (NPP) accident. Although the accident caused no direct radiation-induced casualties, it raised concerns over the safety of NPPs and led to a drop in public acceptance, as well as changes in energy policies in some countries. However, in the medium to long term, prospects for nuclear energy remain positive. A total of 72 reactors were under construction at the beginning of 2014, the highest number in 25 years. Nuclear safety remains the highest priority for the nuclear sector. Regulators have a major role to play to ensure that all operations are carried out with the highest levels of safety. Safety culture must be promoted at all levels in the nuclear sector and especially in newcomer countries. Governments have a role to play in ensuring a stable, long-term investment framework that allows capital-intensive projects to be developed and provides adequate electricity prices over the long term. Governments should also continue to support nuclear R and D, especially in the area of nuclear safety, advanced fuel cycles, waste management and innovative designs. Nuclear energy is a mature low-carbon technology, which has followed a trend towards increased safety levels and power output to benefit from economies of scale. This trajectory has come with an increased cost for Generation III reactors compared with previous generations. Small modular reactors (SMRs) could extend the market for nuclear energy

A Study on Nuclear Technology Policy

International Nuclear Information System (INIS)

Oh, K. B.; Chung, W. S.; Lee, T. J.; Yun, S. W.; Jeong, Ik; Lee, J. H.

2006-02-01

This study was conducted as a part of institutional activities of KAERI, and the objective of the study is to survey and analyze the change of international environment in nuclear use and research and development environment, and to propose systematic alternatives on technology policy for efficiency and effectiveness of research and development through national R and D program while timely responding to the environmental change in local and global sense. In the investigation and analysis of international environmental and technological change 1. Viability of Nuclear Renaissance 2. Recent of Nuclear Technology Policy in Japan 3. Collaboration for Advanced Nuclear Technologies in GIF, INPRO and INERI 4. Nuclear Energy Utilization and Development in Europe. In the evaluation of nuclear technology and sustainable development from the point of views of environmental change 5. External Cost of Environmental Impact in Electric Power Sector 6. Nuclear Technology Development Direction Considering Changes of the Science and Technology Policy Environment 7. Nuclear Energy Development Strategy for a Sustainable National Energy Supply

A Study on Nuclear Technology Policy

Energy Technology Data Exchange (ETDEWEB)

Oh, K B; Chung, W S; Lee, T J; Yun, S W; Jeong, Ik; Lee, J H

2006-02-15

This study was conducted as a part of institutional activities of KAERI, and the objective of the study is to survey and analyze the change of international environment in nuclear use and research and development environment, and to propose systematic alternatives on technology policy for efficiency and effectiveness of research and development through national R and D program while timely responding to the environmental change in local and global sense. In the investigation and analysis of international environmental and technological change 1. Viability of Nuclear Renaissance 2. Recent of Nuclear Technology Policy in Japan 3. Collaboration for Advanced Nuclear Technologies in GIF, INPRO and INERI 4. Nuclear Energy Utilization and Development in Europe. In the evaluation of nuclear technology and sustainable development from the point of views of environmental change 5. External Cost of Environmental Impact in Electric Power Sector 6. Nuclear Technology Development Direction Considering Changes of the Science and Technology Policy Environment 7. Nuclear Energy Development Strategy for a Sustainable National Energy Supply.

Nuclear technology and beyond

International Nuclear Information System (INIS)

Akiyama, Mamoru

1997-01-01

After the confrontation of East and West, and the problem of North and South, we are now facing the era of Globalization in the presence of twenty-first century. Tracing the history of civilization, human being has progressed along with the accumulation of experience, and the development of science and technology. Science and technology bloomed in modern ages, especially, energy technology showed the giant leap in this century. Nuclear science and technology has been developed for peaceful purposes, and for the benefit of humanity. As a result, today, its progress led nuclear science and technology to have the great applicability to the development of the society. Toward the twenty-first century and Globalization, the science and technology developed in nuclear field is hoped to play a great contribution in various area of the society. (author)

Overview of fusion nuclear technology in Europe

Energy Technology Data Exchange (ETDEWEB)

Andreani, R. E-mail: roberto.andreani@tech.efda.org; Gasparotto, M. E-mail: maurizio.gasparotto@tech.efda.org

2002-11-01

The fusion nuclear technology programme in the EU is focussed on materials and breeding blankets development, tritium and high heat flux component technologies. A strong effort is also devoted to the validation of the design of an intense 14 MeV neutron source (IFMIF). The material programme includes the development of reduced activation ferritic martensitic steel (EUROFER) to be used as structural material in a DEMO reactor, and potentially more attractive higher performance materials: ODS and SiC/SiC composites. The breeding blanket activities are focussed in the preparation of the two European Test Blanket Moduli to be installed in ITER. The Fuel Cycle activities for ITER include development of the torus exhaust cryopump, fuel storage system, performance characterisation of the torus exhaust processing and design of water detritiation system. High heat flux components have been developed in the framework of ITER R and D programme and based on copper alloy heat sink protected by an armour of beryllium, CFC or tungsten. Studies give an important contribution in defining the nuclear technology programme strategy.

Overview of fusion nuclear technology in Europe

International Nuclear Information System (INIS)

Andreani, R.; Gasparotto, M.

2002-01-01

The fusion nuclear technology programme in the EU is focussed on materials and breeding blankets development, tritium and high heat flux component technologies. A strong effort is also devoted to the validation of the design of an intense 14 MeV neutron source (IFMIF). The material programme includes the development of reduced activation ferritic martensitic steel (EUROFER) to be used as structural material in a DEMO reactor, and potentially more attractive higher performance materials: ODS and SiC/SiC composites. The breeding blanket activities are focussed in the preparation of the two European Test Blanket Moduli to be installed in ITER. The Fuel Cycle activities for ITER include development of the torus exhaust cryopump, fuel storage system, performance characterisation of the torus exhaust processing and design of water detritiation system. High heat flux components have been developed in the framework of ITER R and D programme and based on copper alloy heat sink protected by an armour of beryllium, CFC or tungsten. Studies give an important contribution in defining the nuclear technology programme strategy

Korean efforts for education and training network in nuclear technology

International Nuclear Information System (INIS)

Han, Kyong-Won; Lee, Eui-Jin

2007-01-01

Nuclear energy has been a backbone for Korea's remarkable economic growth, and will continue its essential role with 18 nuclear power plants in operation, 2 more units under construction, 6 more units in planning. Korea is operating its own designed nuclear power plants, such as KSNP, 1400, as well as self-design and operation of 30 MW Hanaro research reactor. Korea makes strong efforts to develop future nuclear technology. They are the System-Integrated Modular Advanced Reactor, SMART, Korea Advanced Liquid Metal reactor, KALIMER, Hydrogen Production reactor, and Proliferation-resistant Nuclear Fuel Cycle. In parallel, Korea is establishing an Advanced Radiation Technology R and D Center and a High Power Proton Accelerator Center. International, next generation nuclear power technologies are being developed through projects such as the IAEA Innovative Nuclear Reactors and Fuel Cycle, INPRO, Generation IV International Forum, GIF, and International thermonuclear Experimental reactor, ITER. In the new millennium, Korea expects that radiation technology combined with bio, nano, and space technology will sustain our civilization. About 21,000 qualified nuclear human resources are engaged in power and non-power fields such as design and manufacturing of equipment, plant operation and maintenance, safety, RI production, R and D, etc. However, it is recognized that the first generation of nuclear work force is getting older and retired, less of our youth are studying nuclear science and engineering. Korean Government has established a promotion program on nuclear human resources development, which is needed until 2010. For the sustainable development of nuclear science and technology, it calls for more qualified human resources. We ought to encourage our youth to become more interested in nuclear studies and careers. Korea is making strong efforts to support nuclear education and training for young generations. It is believed that internationally accepted advanced

Nuclear technologies for local energy systems

International Nuclear Information System (INIS)

McDonnell, F.N.; Lynch, G.F.

1990-03-01

If nuclear energy is to realize its full potential as a safe and cost-effective alternative to fossil fuels, applications beyond those that are currently being serviced by large, central nuclear power stations must be identified and appropriate reactors developed. The Canadian program on reactor systems for local energy supply is at the forefront of these developments. This program emphasizes design simplicity, low power density and fuel rating, reliance on natural processes, passive systems, and reduced reliance on operator action. The first product, the SLOWPOKE Energy System, is a 10 MW heat source specifically designed to provide hot water to satisfy the needs of local heating systems for building complexes, institutions and municipal district heating systems. A demonstration heating reactor has been constructed at the Whiteshell Nuclear Research Establishment in Manitoba and has been undergoing an extensive test program since first operation in 1987 July. Based on the knowledge learned from the design, construction, licensing and operational testing of this facility, the design of the 10 MW commercial-size unit is well advanced, and Atomic Energy of Canada Limited is prepared to commit the construction of the first commercial unit. Although the technical demonstration of the concept is important, it is recognized that another crucial element is the public and regulatory acceptance of small nuclear systems in urban areas. The decision by a community to commit the construction of a SLOWPOKE Energy System brings to a sharp focus the current public apprehension about nuclear technologies

Design and development of indigenous seismic switch for nuclear reactors

International Nuclear Information System (INIS)

Varghese, Shiju; Shah, Jay; Limaye, P.K.; Soni, N.L; Patel, R.J.

2016-01-01

After Fukushima incident it has become a regulatory requirement to have automatic reactor trip on detection of earthquake beyond OBE level. Seismic Switches that meets the technical specifications required for nuclear reactor use were not available in the market. Hence, on Nuclear Power Corporation of India Ltd (NPCIL's) request, Refuelling Technology Division, BARC has developed Seismic Switches (electronic earthquake detectors) required for this application. Functionality of the system was successfully tested using a Shake Table. Two different designs of seismic switches have been developed. One is a microcontroller based system (digital) and the other is fully analogue electronics (analog) based. These switches are designed to meet the technical requirements of Class IA systems of nuclear reactors. It is also designed to meet other qualification tests such as EMI/EMC, climatic, vibration, and reliability requirements. In addition to nuclear industry seismic switches are having potential use in oil and gas, power plants, buildings and other industrial installations. These technologies are currently available for technology transfer and details are published in BARC website. This paper describes the requirements, principle of operation and features and testing of the developed systems. (author)

Technology transfer in the Spanish nuclear programme

International Nuclear Information System (INIS)

Perez-Naredo, F.

1983-01-01

The paper describes the process of technology transfer under the Spanish nuclear programme and its three generations of nuclear power plants during the last 20 years, with special reference to the nine new plants equipped with Westinghouse pressurized water reactors and the rising level of national involvement in these stations. It deals with the development of Westinghouse Nuclear's organization in Spain, referring to its staff and to the manufacturers who supply equipment for the programme, going into particular detail where problems of quality assurance are concerned. In conclusion, it summarizes the present capacity of Spanish industry in various areas connected with the design, manufacture and construction of nuclear power plants. (author)

Nuclear energy technology

Science.gov (United States)

Buden, David

1992-01-01

An overview of space nuclear energy technologies is presented. The development and characteristics of radioisotope thermoelectric generators (RTG's) and space nuclear power reactors are discussed. In addition, the policy and issues related to public safety and the use of nuclear power sources in space are addressed.

Japanese perspective of fusion nuclear technology from ITER to DEMO

International Nuclear Information System (INIS)

Tanaka, Satoru; Takatsu, Hideyuki

2007-01-01

The world fusion community is now launching construction of ITER, the first nuclear-grade fusion machine in the world. In parallel to the ITER program, Broader Approach (BA) activities are to be initiated in this year by EU and Japan, mainly at Rokkasho BA site in Japan, as complementary activities to ITER toward DEMO. The BA activities include IFMIFEVEDA (International Fusion Materials Irradiation Facility-Engineering Validation and Engineering Design Activities) and DEMO design activities with generic technology R and Ds, both of which are critical to the rapid development of DEMO and commercial fusion power plants. The Atomic Energy Commission of Japan reviewed on-going third phase fusion program and issued the results of the review, 'On the policy of Nuclear Fusion Research and Development' in November 2005. In this report, it is anticipated that the ITER will be made operational in a decade and the programmatic objective can be met in the succeeding seven or eight years. Under this condition, the report presents a roadmap toward the DEMO and beyond and R and D items on fusion nuclear technology, indispensable for fusion energy utilization, are re-aligned. In the present paper, Japanese view and policy on ITER and beyond is summarized mainly from the viewpoints of nuclear fusion technology, and a minimum set of R and D elements on fusion nuclear technology, essential for fusion energy utilization, is presented. (orig.)

Next generation advanced nuclear reactor designs

International Nuclear Information System (INIS)

Turgut, M. H.

2009-01-01

Growing energy demand by technological developments and the increase of the world population and gradually diminishing energy resources made nuclear power an indispensable option. The renewable energy sources like solar, wind and geothermal may be suited to meet some local needs. Environment friendly nuclear energy which is a suitable solution to large scale demands tends to develop highly economical, advanced next generation reactors by incorporating technological developments and years of operating experience. The enhancement of safety and reliability, facilitation of maintainability, impeccable compatibility with the environment are the goals of the new generation reactors. The protection of the investment and property is considered as well as the protection of the environment and mankind. They became economically attractive compared to fossil-fired units by the use of standard designs, replacing some active systems by passive, reducing construction time and increasing the operation lifetime. The evolutionary designs were introduced at first by ameliorating the conventional plants, than revolutionary systems which are denoted as generation IV were verged to meet future needs. The investigations on the advanced, proliferation resistant fuel cycle technologies were initiated to minimize the radioactive waste burden by using new generation fast reactors and ADS transmuters.

The current situation and prospect of fundamental research about nuclear logging technology

International Nuclear Information System (INIS)

Zhang Feng; Wang Xinguang; Yuan Chao

2010-01-01

Nuclear logging technology is one of the important methods to evaluate complex hydrocarbon reservoir in the process of petroleum exploration and development. The fundamental research of nuclear logging is an important step of logging technology innovation. Through analyzing the current situation of the development of nuclear logging technology at home and abroad in recent years, the problems and gaps are pointed out in the field of fundamental research of nuclear logging at home, and the future development of new nuclear logging technologies is concisely analyzed. Therefore, the optimal design and processing are conducted from aspects of ray source, detector, data acquisition and processing method. In addition, the fundamental research of LWD and pulsed neutron logging technology is taken as the main breach. In the fundamental research of nuclear logging technology, innovative thinking should be expressed and the innovation should be achieved in every field of the development of nuclear logging technology. Meanwhile, the logging key lab should be taken as the platform and the latest achievement in the field of nuclear logging technology should be fully utilized. Thus, the level of independent R and D and technology innovation of logging tools will be raised and service for the exploration and development of petroleum and other mineral resources. (authors)

Development of mechanical design technology for integral reactor

Energy Technology Data Exchange (ETDEWEB)

Park, Keun Bae; Choi, Suhn; Kim, Kang Soo; Kim, Tae Wan; Jeong, Kyeong Hoon; Lee, Gyu Mahn

1999-03-01

While Korean nuclear reactor strategy seems to remain focused on the large capacity power generation, it is expected that demand of small and medium size reactor will arise for multi-purpose application such as small capacity power generation, co-generation and sea water desalination. With this in mind, an integral reactor SMART is under development. Design concepts, system layout and types of equipment of integral reactor are significantly different from those of loop type reactor. Conceptual design development of mechanical structures of integral reactor SMART is completed through the first stage of the project. Efforts were endeavored for the establishment of design basis and evaluation of applicable codes and standards. Design and functional requirements of major structural components were setup, and three dimensional structural modelling of SMART reactor vessel assembly was prepared. Also, maintenance and repair scheme as well as preliminary fabricability evaluation were carried out. Since small integral reactor technology includes sensitive technologies and know-how's, it is hard to achieve systematic and comprehensive technology transfer from nuclear-advanced countries. Thus, it is necessary to develop the related design technology and to verify the adopted methodologies through test and experiments in order to assure the structural integrity of reactor system. (author)

Development of mechanical design technology for integral reactor

International Nuclear Information System (INIS)

Park, Keun Bae; Choi, Suhn; Kim, Kang Soo; Kim, Tae Wan; Jeong, Kyeong Hoon; Lee, Gyu Mahn

1999-03-01

While Korean nuclear reactor strategy seems to remain focused on the large capacity power generation, it is expected that demand of small and medium size reactor will arise for multi-purpose application such as small capacity power generation, co-generation and sea water desalination. With this in mind, an integral reactor SMART is under development. Design concepts, system layout and types of equipment of integral reactor are significantly different from those of loop type reactor. Conceptual design development of mechanical structures of integral reactor SMART is completed through the first stage of the project. Efforts were endeavored for the establishment of design basis and evaluation of applicable codes and standards. Design and functional requirements of major structural components were set up, and three dimensional structural modelling of SMART reactor vessel assembly was prepared. Also, maintenance and repair scheme as well as preliminary fabricability evaluation were carried out. Since small integral reactor technology includes sensitive technologies and know-how's, it is hard to achieve systematic and comprehensive technology transfer from nuclear-advanced countries. Thus, it is necessary to develop the related design technology and to verify the adopted methodologies through test and experiments in order to assure the structural integrity of reactor system. (author)

Refer to AP1000 for discussing the betterment of seismic design of internal nuclear power plant

International Nuclear Information System (INIS)

Gong Zhenbang; Zhang Renyan

2014-01-01

As a reference technique of AP1000, This paper discussed the betterment of seismic design of nuclear power plant in three ways. (1) Establish design criteria and guidelines for protection from seismic interaction; (2) Nuclear power plant seismic design of eliminating or weaken operation-basis earthquake; (3) Develop the seismic margin analysis (SMA) of the nuclear power plant. These three aspect are frontier technology in internal seismic design of internal nuclear power plant, and also these three technology are related intimately. (authors)

High degree utilization of computers for design of nuclear power plants

International Nuclear Information System (INIS)

Masui, Takao; Sawada, Takashi

1992-01-01

Nuclear power plants are the huge technology in which various technologies are compounded, and the high safety is demanded. Therefore, in the design of nuclear power plants, it is necessary to carry out the design by sufficiently grasping the behavior of the plants, and to confirm the safety by carrying out the accurate design evaluation supposing the various operational conditions, and as the indispensable tool for these analysis and evaluation, the most advanced computers in that age have been utilized. As to the utilization for the design, there are the fields of design, analysis and evaluation and another fields of the application to the support of design. Also in the field of the application to operation control, computers are utilized. The utilization of computers for the core design, hydrothermal design, core structure design, safety analysis and structural analysis of PWR plants, and for the nuclear design, safety analysis and heat flow analysis of FBR plants, the application to the support of design and the application to operation control are explained. (K.I.)

4+D TechnologyTM for nuclear systems soft solutions

International Nuclear Information System (INIS)

Suh, Kune Y.

2010-10-01

The signature in the proposal lies with the NSSS (Nuclear Systems Soft Solutions). NSSS proposed in the 3-dimensional space and time plus cost coordinates, i.e. 4 + dimensional technology, is the backbone of digital engineering in the nuclear system design and management. The NSSS is empowered by Janus (Junctional Analysis Neo dynamic Unit Soft Power), NOTUS (Neo systemic Optimization Technical Unit Soft Power), Venus (Virtual Engineering Neo cybernetic Unit Soft Power), EURUS (Engineering Utilities Research Unit Soft Power) and INUUS (Informative Neo graphic Utilities Unit Soft Power). Janus extracts the geometric data directly from the computer-aided design CAD files to import to multidimensional computational fluid and structural dynamics codes. Janus uses the joint-CAD analysis methods to eliminate the necessity of any pre- and post- processors. Starting from the 3-dimensional CAD, NOTUS contributes to reducing the construction cost of the nuclear power plants by optimizing the component manufacturing procedure and the plant construction process. Planning and scheduling construction projects can thus benefit greatly by integrating traditional management techniques with digital process simulation visualization. The 3-dimensional visualization of construction processes and resulting products intrinsically afford most of the advantages realized by the 4 + D technology. Problems with equipment positioning and manpower congestion in certain areas can readily be visualized prior to the actual operation, thus preventing accidents and safety problems such as collision between two machines and losses in productivity. Venus applied the virtual reality technology in nuclear industry. Virtual reality provides an interactive real time motion with sound and tactile and other forms of feedback. The management and workers can thus comprehend the work process crystal clear by visualizing precisely how activities relate to one another, whereby reducing conflicting

Meeting cross-section requirements for nuclear-energy design

Energy Technology Data Exchange (ETDEWEB)

Weisbin, C.R.; de Saussure, G.; Santoro, R.T. (Oak Ridge National Lab., TN (USA)); Gilai, T. (Ben-Gurion Univ. of the Negev, Beersheba (Israel))

1982-01-01

Current requirements in cross-section data that are essential to nuclear-energy programmes are summarized and explained and some insight into how these data might be obtained is provided. The six sections of the paper describe: design parameters and target accuracies; data collection, evaluation and analysis; determination of high-accuracy differential nuclear data for technological applications; status of selected evaluated nuclear data; analysis of benchmark testing; identification of important cross sections and inferred needs.

Nuclear technology options

International Nuclear Information System (INIS)

Salvatores, Massimo

2013-01-01

Different strategies and motivations in different countries have led to diverse options. In Europe the SNETP (Sustainable Nuclear Energy Technology Platform) has the objective of developing R&D supporting GEN-II (present) and GEN-III nuclear systems under development; allowing sustainability and minimisation of waste burden, promoting advanced Gen-IV Fast Reactors; and accounting for a Nuclear Cogeneration Industrial Initiative. A remarkable initiative in the USA has been the promotion of small modular reactors (SMRs) – at less than 300 MWe in capacity, much smaller than typical reactors – which can be an ideal choice for (remote) areas which cannot support a larger reactor. Compact scalable design offers a host of potential safety, construction and economic benefits. More “upbeat” strategies are expected in other areas of the world where significant increase in nuclear energy demand is predicted in the next decades. If this growth materialises, future fuel cycles characteristics, feasibility and acceptability will be crucial. This paper will discuss different scenarios for future fuel cycles, resources optimisation and/or waste minimization, the range from full fast reactor deployment to phase-out, management of spent nuclear fuel and the significant potential benefits of advanced cycles. The next 45 years will be dominated by deployment of standard large or medium size plants operating for 60 years. Available resources do allow it. However, fuel cycle will be a growing and most challenging issue and early assessments will be needed for public acceptance and policy decisions.

Shield design development of nuclear propulsion merchant ship

International Nuclear Information System (INIS)

Tanaka, Yoshihisa

1975-01-01

Shielding design both in Japan and abroad for nuclear propulsion merchant ships is explained, with emphasis on the various technological problems having occurred in the shield design for one-body type and separate type LWRs as conceptual design. The following matters are described: the peculiarities of the design as compared with the case of land-based nuclear reactors, problems in the design standards of shielding, the present status and development of the design methods, and the instances of the design; thereby, the trends of shielding design are disclosed. The following matters are pointed out: Importance of the optimum design, of shielding, significance of radiation streaming through large voids, activation of the secondary water in built-in type steam generators, and the need of the guides for shield design. (Mori, K.)

GE's advanced nuclear reactor designs

International Nuclear Information System (INIS)

Berglund, R.C.

1993-01-01

The excess of US electrical generating capacity which has existed for the past 15 years is coming to an end as we enter the 1990s. Environmental and energy security issues associated with fossil fuels are kindling renewed interest in the nuclear option. The importance of these issues are underscored by the National Energy Strategy (NES) which calls for actions which open-quotes are designed to ensure that the nuclear power option is available to utilities.close quotes Utilities, utility associations, and nuclear suppliers, under the leadership of the Nuclear Power Oversight Committee (NPOC), have jointly developed a 14-point strategic plan aimed at establishing a predictable regulatory environment, standardized and pre-licensed Advanced Light Water Reactor (ALWR) nuclear plants, resolving the long-term waste management issue, and other open-quotes enabling conditions.close quotes GE is participating in this national effort and GE's family of advanced nuclear power plants feature two reactor designs, developed on a common technology base, aimed at providing a new generation of nuclear plants to provide safe, clean, economical electricity to the world's utilities in the 1990s and beyond. Together, the large-size (1300 MWe) Advanced Boiling Water Reactor (ABWR) and the small-size (600 MWe) Simplified Boiling Water Reactor (SBWR) are innovative, near-term candidates for expanding electrical generating capacity in the US and worldwide. Both possess the features necessary to do so safety, reliably, and economically

Technical Integration of Nuclear Hydrogen Production Technology

International Nuclear Information System (INIS)

Lee, Ki Young; Chang, J. H.; Park, J. K.

2007-06-01

These works focus on the development of attainment indices for nuclear hydrogen key technologies, the analysis of the hydrogen production process and the performance estimation for hydrogen production system, and the assessment of the nuclear hydrogen production economy. To estimate the attainments of the key technologies in progress with the performance goals of GIF, itemized are the attainment indices based on SRP published in VHTR R and D steering committee of Gen-IV. For assessing the degree of attainments in comparison with the final goals of VHTR technologies in progress of researches, subdivided are the prerequisite items conformed to the NHDD concepts established in a preconceptual design in 2005. The codes for analyzing the hydrogen production economy are developed for calculating the unit production cost of nuclear hydrogen. We developed basic R and D quality management methodology to meet design technology of VHTR's needs. By putting it in practice, we derived some problems and solutions. We distributed R and D QAP and Q and D QAM to each teams and these are in operation. Computer simulations are performed for estimating the thermal efficiency for the electrodialysis component likely to adapting as one of the hydrogen production system in Korea and EED-SI process known as the key components of the hydrogen production systems. Using the commercial codes, the process diagrams and the spread-sheets were produced for the Bunsen reaction process, Sulphuric Acid dissolution process and HI dissolution process, respectively, which are the key components composing of the SI process

Why nuclear technology

International Nuclear Information System (INIS)

Vieira, Wilson J.; Ishiguro, Yuji; Urbina, Ligia M. Soto

1996-01-01

The importance of nuclear energy in the global society implies the nacional need to give priority and maintain an effective technology policy for nuclear science. In this work, it is considered three points that, although do not represent all the problems in the nuclear sector, were chosen because of their importance and need of change that require: evaluation of the Brazilian scientific policy, which is directed towards the publication in international periodicals, yielding more benefits to the developed countries; evaluation of the few and small investment in laboratories and research institutes, which are the natural producers of technology for the industry and service sectors; evaluation of the lack of concrete of concrete objectives in the universities and research institutes, whose policies are elaborated with-out the due consideration of the collective benefits. It is necessary a national plan for the nuclear are that makes investments in technology development, investments in the laboratories and research institutes, and that makes these universities and research institutes accountable for the success or failure to accomplish the proposed objectives. (author)

Introduction to nuclear technology

International Nuclear Information System (INIS)

Goldsmith, M.W.

1985-01-01

In the late 1940s and early 1950s when nuclear technology emerged, there was no oil embargo or any obvious signs of an energy crisis. The driving forces for the rapid development of the atom were its fuel efficiency and its potential cost-effectiveness compared to its alternatives. Uranium was a cheap and abundant domestic fuel and the development of the technology provided new vistas and challenges for the engineering community. It was the goal of providing environmentally clean, abundant, and reasonably priced energy that motivated engineers then as now. Nuclear technology developed under a mixture of government regulation and promotion and utility industry commercialization. This paper discusses the development and implementation of a technology largely resulting from the efforts of government to make the production of nuclear-powered electricity a commercial enterprise. This effort has largely succeeded, as greater than 10% of the electricity generated nationally is now provided by nuclear power

A Study on the Nuclear Technology Policy

International Nuclear Information System (INIS)

Lim, C. Y.; Lee, K. S.; Jeong, I.; Lee, J. H.

2009-04-01

The objective of the study was to make policy-proposes for enhancing the effectiveness and efficiency of national nuclear technology development programs. To do this, recent changes of international nuclear energy policy and trends of nuclear technology R and D was surveyed and analyzed. In the viewpoint of analysis of the changes in the global policy surrounding nuclear technology development and development of national nuclear R and D strategy, this study (1) analyzed the trends of nuclear technology policies and (2) discussed the mid and long term strategy of nuclear energy R and D. To put it in more detail, each subject was further explored as follows; (1) analyzed the trends of nuclear technology policies - Trend and prospects of the international and domestic nuclear policies - Investigation of development of small and medium sized policies - International collaboration for advanced nuclear technologies (2) discussed the mid and long term strategy of nuclear energy R and D - The long term development plan for future nuclear energy system - The facilitation of technology commercialization

A Study on the Nuclear Technology Policy

Energy Technology Data Exchange (ETDEWEB)

Kim, H. J.; Lim, C. Y.; Yang, M. H. (and others)

2008-03-15

The objective of the study was to make policy-proposes for enhancing the effectiveness and efficiency of national nuclear technology development programs. To do this, changes of international nuclear energy policy environment and trends of nuclear technology development was surveyed and analyzed. In the viewpoint of analysis of the changes in the global policy environment surrounding nuclear technology development and development of national nuclear R and D strategy, this study (1) analyzed trends of nuclear technology policies and (2) developed the nuclear energy R and D innovation strategies. To put it in more detail, each subject was further explored as follows; (1) themes to analyze trends of nuclear policies: nuclear Renaissance and forecast for nuclear power plant, International collaboration for advanced nuclear technologies in GIF, INPRO and I-NERI, The present situation and outlook for world uranium market (2) themes to develop of nuclear energy R and D innovation strategies: The mid-term strategy plan of the KAERI, The technological innovation case of the KAERI.

A Study on the Nuclear Technology Policy

International Nuclear Information System (INIS)

Kim, H. J.; Lim, C. Y.; Yang, M. H.

2008-03-01

The objective of the study was to make policy-proposes for enhancing the effectiveness and efficiency of national nuclear technology development programs. To do this, changes of international nuclear energy policy environment and trends of nuclear technology development was surveyed and analyzed. In the viewpoint of analysis of the changes in the global policy environment surrounding nuclear technology development and development of national nuclear R and D strategy, this study (1) analyzed trends of nuclear technology policies and (2) developed the nuclear energy R and D innovation strategies. To put it in more detail, each subject was further explored as follows; (1) themes to analyze trends of nuclear policies: nuclear Renaissance and forecast for nuclear power plant, International collaboration for advanced nuclear technologies in GIF, INPRO and I-NERI, The present situation and outlook for world uranium market (2) themes to develop of nuclear energy R and D innovation strategies: The mid-term strategy plan of the KAERI, The technological innovation case of the KAERI

A framework for AI-based nuclear design support system

International Nuclear Information System (INIS)

Furuta, Kazuo; Kondo, Shunsuke

1991-01-01

Nowadays many computer programs are being developed and used for the analytic tasks in nuclear reactor design, but experienced designers are still responsible for most of the synthetic tasks which are not amenable to algorithmic computer processes. Artificial intelligence (AI) is a promising technology to deal with these intractable tasks in design. In development of AI-based design support systems, it is desirable to choose a comprehensive framework based on the scientific theory of design. In this work a framework for AI-based design support systems for nuclear reactor design will be proposed based on an exploration model of design. The fundamental architectures of this framework will be described especially on knowledge representation, context management and design planning. (author)

Nuclear Technology Programs

International Nuclear Information System (INIS)

Harmon, J.E.

1990-10-01

This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April--September 1988. These programs involve R ampersand D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned with examining the feasibility of substituting low-enriched for high-enriched uranium in the production of fission-product 99 Mo. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories

Nuclear technology programs

International Nuclear Information System (INIS)

Harmon, J.E.

1992-01-01

This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1989--March 1990. These programs involve R ampersand D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of metal fuel and blanket materials of the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned water waste stream generated in production of 2,4,6-trinitrotoluene. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories

Nuclear Technology Programs

Energy Technology Data Exchange (ETDEWEB)

Harmon, J.E. (ed.)

1990-10-01

This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April--September 1988. These programs involve R D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned with examining the feasibility of substituting low-enriched for high-enriched uranium in the production of fission-product {sup 99}Mo. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories.

Nuclear technology review 2004

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-08-15

The viability and credibility of a wide range of nuclear-based technologies require ready access to high-quality atomic, molecular and nuclear data. The demands of new nuclear technologies continue to determine the direction(s) of future data development, including the requirements for data that address innovative fuel cycles, accelerator-driven systems, nuclear incineration, fusion devices, diagnostic and therapeutic medical treatment by radiation, optimization of medical isotope production, non-destructive materials testing, radiation analytical techniques, minerals exploration and land-mine detection. Some recent data development projects with diverse applications are a search engine for Atomic and Molecular data to permit simultaneous data retrieval from a number of different sources for both numerical and bibliographic databases to aid designers. For over 50 years, research reactors have made valuable contributions to the development of nuclear power, basic science, materials development, radioisotope production for medicine and industry, and education and training. They remain core experimental instruments. As of June 2004, 672 research reactors are recorded in the IAEA's Research Reactor Data Base (RRDB), of which 274 are operational in 56 countries (85 in 39 developing countries), 214 are shut down, 168 have been decommissioned and 16 are planned or under construction. Nuclear power supplied 16% of global electricity generation in 2002, and as of 31 December 2003 there were 439 NPPs operating worldwide. Their global energy availability factor has risen steadily from 74.2% in 1991 to approximately 84% in 2003. In 2003 two new NPPs were connected to the grid, a 665 MW(e) pressurized heavy water reactor (PHWR) in China and a 960 MW(e) pressurized water reactor (PWR) in the Republic of Korea. In addition Canada restarted two units that had been shutdown. Construction started on one new NPP in India. Four 50 MW(e) units in the UK were retired, as were one 640 MW

Nuclear technology review 2004

International Nuclear Information System (INIS)

2004-08-01

The viability and credibility of a wide range of nuclear-based technologies require ready access to high-quality atomic, molecular and nuclear data. The demands of new nuclear technologies continue to determine the direction(s) of future data development, including the requirements for data that address innovative fuel cycles, accelerator-driven systems, nuclear incineration, fusion devices, diagnostic and therapeutic medical treatment by radiation, optimization of medical isotope production, non-destructive materials testing, radiation analytical techniques, minerals exploration and land-mine detection. Some recent data development projects with diverse applications are a search engine for Atomic and Molecular data to permit simultaneous data retrieval from a number of different sources for both numerical and bibliographic databases to aid designers. For over 50 years, research reactors have made valuable contributions to the development of nuclear power, basic science, materials development, radioisotope production for medicine and industry, and education and training. They remain core experimental instruments. As of June 2004, 672 research reactors are recorded in the IAEA's Research Reactor Data Base (RRDB), of which 274 are operational in 56 countries (85 in 39 developing countries), 214 are shut down, 168 have been decommissioned and 16 are planned or under construction. Nuclear power supplied 16% of global electricity generation in 2002, and as of 31 December 2003 there were 439 NPPs operating worldwide. Their global energy availability factor has risen steadily from 74.2% in 1991 to approximately 84% in 2003. In 2003 two new NPPs were connected to the grid, a 665 MW(e) pressurized heavy water reactor (PHWR) in China and a 960 MW(e) pressurized water reactor (PWR) in the Republic of Korea. In addition Canada restarted two units that had been shutdown. Construction started on one new NPP in India. Four 50 MW(e) units in the UK were retired, as were one 640 MW

Development of core design and analyses technology for integral reactor

International Nuclear Information System (INIS)

Zee, Sung Quun; Lee, C. C.; Kim, K. Y.

2002-03-01

In general, small and medium-sized integral reactors adopt new technology such as passive and inherent safety concepts to minimize the necessity of power source and operator actions, and to provide the automatic measures to cope with any accidents. Specifically, such reactors are often designed with a lower core power density and with soluble boron free concept for system simplification. Those reactors require ultra long cycle operation for higher economical efficiency. This cycle length requirement is one of the important factors in the design of burnable absorbers as well as assurance of shutdown margin. Hence, both computer code system and design methodology based on the today's design technology for the current commercial reactor cores require intensive improvement for the small and medium-sized soluble boron free reactors. New database is also required for the development of this type of reactor core. Under these technical requirements, conceptual design of small integral reactor SMART has been performed since July 1997, and recently completed under the long term nuclear R and D program. Thus, the final objectives of this work is design and development of an integral reactor core and development of necessary indigenous design technology. To reach the goal of the 2nd stage R and D program for basic design of SMART, design bases and requirements adequate for ultra long cycle and soluble boron free concept are established. These bases and requirements are satisfied by the core loading pattern. Based on the core loading pattern, nuclear, and thermal and hydraulic characteristics are analyzed. Also included are fuel performance analysis and development of a core protection and monitoring system that is adequate for the soluble boron free core of an integral reactor. Core shielding design analysis is accomplished, too. Moreover, full scope interface data are produced for reactor safety and performance analyses and other design activities. Nuclear, thermal and

An integral reactor design concept for a nuclear co-generation plant

International Nuclear Information System (INIS)

Lee, D.J.; Kim, J.I.; Kim, K.K.; Chang, M.H.; Moon, K.S.

1997-01-01

An integral reactor concept for nuclear cogeneration plant is being developed at KAERI as an attempt to expand the peaceful utilization of well established commercial nuclear technology, and related industrial infrastructure such as desalination technology in Korea. Advanced technologies such as intrinsic and passive safety features are implemented in establishing the design concepts to enhance the safety and performance. Research and development including laboratory-scale tests are concurrently underway to evaluate the characteristics of various passive safety concepts and provide the proper technical data for the conceptual design. This paper describes the preliminary safety and design concepts of the advanced integral reactor. Salient features of the design are hexagonal core geometry, once-through helical steam generator, self-pressurizer, and seismic resistant fine control CEDMS, passive residual heat removal system, steam injector driven passive containment cooling system. (author)

Nuclear vapor thermal reactor propulsion technology

International Nuclear Information System (INIS)

Maya, I.; Diaz, N.J.; Dugan, E.T.; Watanabe, Y.; McClanahan, J.A.; Wen-Hsiung Tu; Carman, R.L.

1993-01-01

The conceptual design of a nuclear rocket based on the vapor core reactor is presented. The Nuclear Vapor Thermal Rocket (NVTR) offers the potential for a specific impulse of 1000 to 1200 s at thrust-to-weight ratios of 1 to 2. The design is based on NERVA geometry and systems with the solid fuel replaced by uranium tetrafluoride (UF 4 ) vapor. The closed-loop core does not rely on hydrodynamic confinement of the fuel. The hydrogen propellant is separated from the UF 4 fuel gas by graphite structure. The hydrogen is maintained at high pressure (∼100 atm), and exits the core at 3,100 K to 3,500 K. Zirconium carbide and hafnium carbide coatings are used to protect the hot graphite from the hydrogen. The core is surrounded by beryllium oxide reflector. The nuclear reactor core has been integrated into a 75 klb engine design using an expander cycle and dual turbopumps. The NVTR offers the potential for an incremental technology development pathway to high performance gas core reactors. Since the fuel is readily available, it also offers advantages in the initial cost of development, as it will not require major expenditures for fuel development

To MARS and Beyond with Nuclear Power - Design Concept of Korea Advanced Nuclear Thermal Engine Rocket

Energy Technology Data Exchange (ETDEWEB)

Nam, Seung Hyun; Chang, Soon Heung [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

2013-05-15

The President Park of ROK has also expressed support for space program promotion, praising the success of NARO as evidence of a positive outlook. These events hint a strong signal that ROK's space program will be accelerated by the national eager desire. In this national eager desire for space program, the policymakers and the aerospace engineers need to pay attention to the advanced nuclear technology of ROK that is set to a major world nuclear energy country, even exporting the technology. The space nuclear application is a very much attractive option because its energy density is the most enormous among available energy sources in space. This paper presents the design concept of Korea Advanced Nuclear Thermal Engine Rocket (KANuTER) that is one of the advanced nuclear thermal rocket engine developing in Korea Advanced Institute of Science and Technology (KAIST) for space application. Solar system exploration relying on CRs suffers from long trip time and high cost. In this regard, nuclear propulsion is a very attractive option for that because of higher performance and already demonstrated technology. Although ROK was a late entrant into elite global space club, its prospect as a space racer is very bright because of the national eager desire and its advanced technology. Especially it is greatly meaningful that ROK has potential capability to launch its nuclear technology into space as a global nuclear energy leader and a soaring space adventurer. In this regard, KANuTER will be a kind of bridgehead for Korean space nuclear application.

To MARS and Beyond with Nuclear Power - Design Concept of Korea Advanced Nuclear Thermal Engine Rocket

International Nuclear Information System (INIS)

Nam, Seung Hyun; Chang, Soon Heung

2013-01-01

The President Park of ROK has also expressed support for space program promotion, praising the success of NARO as evidence of a positive outlook. These events hint a strong signal that ROK's space program will be accelerated by the national eager desire. In this national eager desire for space program, the policymakers and the aerospace engineers need to pay attention to the advanced nuclear technology of ROK that is set to a major world nuclear energy country, even exporting the technology. The space nuclear application is a very much attractive option because its energy density is the most enormous among available energy sources in space. This paper presents the design concept of Korea Advanced Nuclear Thermal Engine Rocket (KANuTER) that is one of the advanced nuclear thermal rocket engine developing in Korea Advanced Institute of Science and Technology (KAIST) for space application. Solar system exploration relying on CRs suffers from long trip time and high cost. In this regard, nuclear propulsion is a very attractive option for that because of higher performance and already demonstrated technology. Although ROK was a late entrant into elite global space club, its prospect as a space racer is very bright because of the national eager desire and its advanced technology. Especially it is greatly meaningful that ROK has potential capability to launch its nuclear technology into space as a global nuclear energy leader and a soaring space adventurer. In this regard, KANuTER will be a kind of bridgehead for Korean space nuclear application

Planning of the development of the MMIS core technology based on nuclear-IT convergence

International Nuclear Information System (INIS)

Kwon, Kee Choon; Kim, Chang Hwoi; Hwang, In Koo

2012-01-01

- Drive nuclear-IT convergence technologies such as middleware applied new concept nuclear instrumentation and control architecture, automated operation of future nuclear power plant, virtual reality/augmented reality, design and verification technology of a nuclear power plant main control room, software dependability, and cyber security technology - Write state-of-the-art report for the nuclear instrumentation and control based on IT convergence - A prototype which implemented related equipment and software subject to nuclear reactor operator that reside in the main control room (Reactor Operator, RO) order to a on-site operator (Local Operator, LO) and confirm the task performance matches the RO's intention - 'IT Convergence intelligent instrumentation and control technology' project planning for the Fourth Nuclear Power Research and Development in the long-term plan

Nuclear Technology applications

International Nuclear Information System (INIS)

Cibils Machado, W. E- mail: wrcibils@adinet.com.uy

2002-01-01

The present work tries on the applications of the nuclear technology in the life daily, such as agriculture and feeding, human health, industry, non destructive essays, isotopic hydrology, and the nuclear power stations for electricity production and radioisotopes production

3. General principles of assessing seismic resistance of technological equipment of nuclear power plants

International Nuclear Information System (INIS)

1983-01-01

The evaluation of the seismic resistance of technological equipment is performed by computation, experimental trial, possibly by combining both methods. Existing and prepared standards in the field of seismic resistance of nuclear power plants are mentioned. Accelerograms and response spectra of design-basis earhtquake and maximum credible earthquake serve as the basic data for evaluating seismic resistance. The nuclear power plant in Mochovce will be the first Czechoslovak nuclear power plant with so-called partially seismic design. The problem of dynamic interaction of technological equipment and nuclear power plant systems with a bearing structure is discussed. (E.F.)

Overview of space nuclear technologies and the American Nuclear Society

International Nuclear Information System (INIS)

Singleterry, R.C. Jr.

2000-01-01

The American Nuclear Society (ANS) has seen an aspect of the universe where nuclear technology is the best energy source available for power, transportation, etc. The National Aeronautics and Space Administration (NASA) has been exploiting this aspect of the universe by sending machines and humans into it and exploring, colonizing, industrializing, developing, inhabiting, etc. Space is the final frontier, and nuclear technology is the best suited for today's or the next century's space exploration and development. Many aspects of nuclear technology and its uses in space will be needed. ANS encompasses these and many more aspects of nuclear technology, and all have some role to play in the exploration and development of space. It should be ANS's intent to be an advisory body to NASA on the nuclear aspects of space exploration

Indian Nuclear Society annual conference-1994 on advanced technologies related to nuclear power: proceedings

International Nuclear Information System (INIS)

Grover, R.B.

1994-01-01

The focal theme of the conference is advanced technologies related to nuclear power. Over the past three decades civilian nuclear power plants around the world have accumulated about 6000 reactor years of experience and have performed quite well. Overall safety record has been satisfactory. However, nuclear community is trying to compete with its own record by trying to enhance the safety characteristics of the best operating plant. A safety culture has been established in the nuclear establishments, which is providing impetus to advances in all aspects of nuclear technology all over the world. India has ongoing programmes for the development of advanced reactors and related advanced technologies. Evolution of pressurised heavy water reactors in India, developments made in the design of advanced heavy water reactor and the fast reactor programme, are some of the topics covered in addition to highlighting worldwide developments for the next generation of light water reactors. India is one of the few countries in the world where expertise about complete fuel cycle is available. Developments in the back end of the fuel cycle, use of thorium and plutonium and other related issues are also discussed. Technology control regimes being advocated and adopted by developed nations make it imperative for us to indigenise every equipment and component that goes into a power plant. In view of this, some aspects of manufacturing technologies, inspection techniques and maintenance problems are also covered. Relevant papers are processed separately for INIS. (M.K.V.)

Toshiba integrated information system for design of nuclear power plants

International Nuclear Information System (INIS)

Abe, Yoko; Kawamura, Hirobumi; Sasaki, Norio; Takasaka, Kiyoshi

1993-01-01

TOSHIBA aims to secure safety, increase reliability and improve efficiency through the engineering for nuclear power plants and has been introducing Computer Aided Engineering (CAE). Up to the present, TOSHIBA has been developing computer systems which support each field of design and applying them to the design of nuclear power plants. The new design support system has been developed to integrate each of those systems in order to realize much greater improvement in accuracy and increase of reliability in design using state-of-the-art computer technology

The roles and functions of a lunar base Nuclear Technology Center

International Nuclear Information System (INIS)

Buden, D.; Angelo, J.A. Jr.

1991-01-01

This paper describes the roles and functions of a special Nuclear Technology Center which is developed as an integral part of a permanent lunar base. Numerous contemporary studies clearly point out that nuclear energy technology will play a major role in any successful lunar/Mars initiative program and in the overall establishment of humanity's solar system civilization. The key role of nuclear energy in the providing power has been recognized. A Nuclear Technology Center developed as part of of a permanent lunar base can also help bring about many other nuclear technology applications, such as producing radioisotopes for self-illumination, food preservation, waste sterilization, and medical treatment; providing thermal energy for mining, materials processing and agricultural; and as a source of emergency habitat power. Designing such a center will involve the deployment, operation, servicing and waste product management and disposal of megawatt class reactor power plants. This challenge must be met with a minimum of direct human support at the facility. Furthermore, to support the timely, efficient integration of this Nuclear Technology Center in the evolving lunar base infrastructure, an analog of such a facility will be needed here on Earth. 12 refs., 4 figs., 1 tab

FPGA-based technology for Pulse Height Analysis in nuclear spectrometry system

International Nuclear Information System (INIS)

Andrianiaina, H.; Raoelina Andriambololona; Rajaobelison, J.; Rambolamanana, G.; Roengen, H.

2009-01-01

Facing the rapid technology development applied in nuclear instruments, Madagascar-INSTN has taken measures to estabilish and enhance the national capabilities in their maintenance, calibration, design/modification and repair, which is a key factor in the development of sustainable nuclear technology.The maintenance will be more convenient if all technical resources are made available: this is only possible when the acces to designer side of the instruments is permitted. Research and instrumentation development projects have been developed to support and to fit the local needs: Pulse Height Analysis algorithm is designed within FPGA and VHDL programming technics to build a Multi-Input Multi-Channel Analyzer. Description and measurement results with the MIMCA will be described in the present paper

A Study on the Nuclear Technology Policy

International Nuclear Information System (INIS)

Oh, K. B.; Lee, K. S.; Chung, W. S.; Lee, T. J.; Yun, S. W.; Jeong, I.; Lee, J. H.

2007-02-01

The objective of the study was to make policy-proposals for enhancing the effectiveness and efficiency of national nuclear technology R and D programs. To do this, environmental changes of international nuclear energy policy and trends of nuclear technology development were surveyed and analyzed. This Study analyzed trends of nuclear technology policies and developed the nuclear energy R and D innovation strategy in a viewpoint of analyzing the changes in the global policy environment associated with nuclear technology development and development of national nuclear R and D strategy

Current status and future prospects of Korean standardized nuclear power plant design

International Nuclear Information System (INIS)

Rieh, C.-H.; Park, S.-K.; Lee, B.-R.

1992-01-01

The authors reviewed a brief history of Korean nuclear industry since the first Kori-1 plant operation in 1978 with special emphasis on the NSSS and BOP design and engineering, and the design approaches for nuclear power plants in the future. Continued effort to enhance plant economy and operational safety has been made by increasing plant size, and improving safety features, systems and component reliability in various design aspects. Korean nuclear industry is now trying to be one of the major contributors to the world nuclear field in sharing nuclear technology gained from past experience and developed through internation technical cooperation programs

Framework for AI-based nuclear reactor design support system

International Nuclear Information System (INIS)

Furuta, Kazuo; Kondo, Shunsuke

1992-01-01

Nowadays many computer programs are being developed and used for the analytic tasks in nuclear reactor design, but experienced designers are still responsible for most of the synthetic tasks which are not amenable to algorithmic computer processes. Artificial intelligence (AI) is a promising technology to deal with these intractable tasks in design. In development of AI-based design support systems, it is desirable to choose a comprehensive framework based on the scientific theory of design. In this work a framework for AI-based design support systems for nuclear reactor design will be proposed based on an explorative abduction model of design. The fundamental architectures of this framework will be described especially on knowledge representation, context management and design planning. (author)

Nuclear power. Volume 1. Nuclear power plant design

International Nuclear Information System (INIS)

Pedersen, E.S.

1978-01-01

NUCLEAR POWER PLANT DESIGN is intended to be used as a working reference book for management, engineers and designers, and as a graduate-level text for engineering students. The book is designed to combine theory with practical nuclear power engineering and design experience, and to give the reader an up-to-date view of the status of nuclear power and a basic understanding of how nuclear power plants function. Volume 1 contains the following chapters; (1) nuclear reactor theory; (2) nuclear reactor design; (3) types of nuclear power plants; (4) licensing requirements; (5) shielding and personnel exposure; (6) containment and structural design; (7) main steam and turbine cycles; (8) plant electrical system; (9) plant instrumentation and control systems; (10) radioactive waste disposal (waste management) and (11) conclusion

Lifetime Management in Non-US-Technology Nuclear Power Plants using US Regulations

International Nuclear Information System (INIS)

Cornelius Steenkamp, J.; Encabo Espartero, J.; Garcia Iglesias, R.

2013-01-01

In July 2009 the Spanish Nuclear Regulator (CSN) issued a Safety Instruction (IS-22) for the development of Lifetime Management in the Nuclear Power Plants within Spain. The context of this Safety Instruction is based on the American Regulations 10CFR54, NUREG1800/1801 and the technical guide NEI95-10. All these regulations are aimed at US-Technology Nuclear Power Plants. Lifetime Management of Nuclear Power Plants with a plant design different from US technologies can most certainly be developed with the mentioned US regulations. The successful development of Lifetime Management in these cases depends on the adaptation of the different requirements of the regulations. Challenges resulting from the adaptation process can be resolved by taking into consideration the plant design of the plant in question.

A study on the nuclear technology policy

International Nuclear Information System (INIS)

Kim, H. J.; Oh, K. B.; Chung, W. S.; Lee, T. J.; Yun, S. W.; Jeong, Ik

2005-01-01

This study was conducted as a part of institutional activities of KAERI, and the objective of the study is to survey and analyze the change of international environment in nuclear use and research and development environment, and to propose systematic alternatives on technology policy for efficiency and effectiveness of research and development through national R and D program while timely responding to the environmental change in local and global sense. Acknowledging the importance of the relationship between the external environment and the national nuclear R and D strategic planning for changing of environment of surrounding nuclear technology and development in the world, this study focused on the three major subjects: (1) investigation and analysis of international nuclear environmental and technological change; (2) developing nuclear R and D strategy based on the analysis of national and global environment surrounding nuclear technology development and diffusion; (3) the evaluation of role of nuclear technology and environment from the point of views of environmental effects. In order to enhance the role of national nuclear R and D program and to cope with the environmental and technological change surrounding nuclear energy, it is recommended that active participation should be done in ongoing international collaboration on future innovative nuclear technology for absorption of advanced technologies and strategic R and D planning should be centered on core technology field based on long-term vision and suggested NuTRM considering future energy-environmental surroundings for maximized use of domestic technology capabilities and resources

Pakistan's experience in transfer of nuclear technology

International Nuclear Information System (INIS)

Ahmad Khan, Nunir

1977-01-01

Of all technologies, nuclear technology is perhaps the most interdisciplinary in character as it encompasses such varied fields as nuclear physics, reactor physics, mechanical, electrical electronics controls, metallurgical and even civil and geological engineering. When we speak of transfer of acquisition of nuclear technology we imply cumulative know-how in many fields, most of which are not nuclear per se but are essential for building the necessry infrastructure and back-up facilities for developing and implementing any nuclear energy program. In Pakistan, efforts on utilization of nuclear energy for peaceful applications were initiated about twenty years ago. During these years stepwise development of nuclear technology has taken place. The experience gained by Pakistan so far in transfer of nuclear technology is discussed. Suggestions have been made for continuing the transfer of this most essential technology from the advanced to the developing countries while making sure that necessary safeguard requirements are fullfilled

Digital Process Management Technology for Nuclear Power Plants

International Nuclear Information System (INIS)

You, Young M.; Suh, Kune Y.

2009-01-01

PHILOSOPHIA, Inc. and Seoul National University have utilized the cutting edge Digital Process Management (DPM) technology for the good of Nuclear Power Plant in recent days. This work represent the overall benefits and the use of this new flow of technology which come into the spotlight. Before realizing the three dimensional (3D) technologies and applying it to real mechanical manufactures and constructions, majority of planning and designing works need huge time and cost even if the process is before the real work. Especially, for a massive construction such as power plant and harbor, without computer-aided technology currently we cannot imagine the whole process can be established easily. Computer-aided Design (CAD) is now main and common technology for manufacturing or construction. This technology lead the other virtual reality 3D technologies into the job site. As a member of these new technologies, DPM is utilized in high-tech and huge scale manufacturing and construction for the benefits of time and cost

Planning of the development of the MMIS core technology based on nuclear-IT convergence

Energy Technology Data Exchange (ETDEWEB)

Kwon, Kee Choon; Kim, Chang Hwoi; Hwang, In Koo [KAERI, Daejeon (Korea, Republic of); and others

2012-01-15

- Drive nuclear-IT convergence technologies such as middleware applied new concept nuclear instrumentation and control architecture, automated operation of future nuclear power plant, virtual reality/augmented reality, design and verification technology of a nuclear power plant main control room, software dependability, and cyber security technology - Write state-of-the-art report for the nuclear instrumentation and control based on IT convergence - A prototype which implemented related equipment and software subject to nuclear reactor operator that reside in the main control room (Reactor Operator, RO) order to a on-site operator (Local Operator, LO) and confirm the task performance matches the RO's intention - 'IT Convergence intelligent instrumentation and control technology' project planning for the Fourth Nuclear Power Research and Development in the long-term plan.

Development of nuclear power plant simulators for Soviet-designed nuclear reactors

International Nuclear Information System (INIS)

Kohut, P.; Tutu, N.K.; Cleary, E.J.; Erickson, K.G.; Yoder, J.; Kroshilin, A.

2001-01-01

The US Department of Energy (US DOE), under the US government's International Nuclear Safety Program (INSP), is implementing a program of developing and providing simulators for many of the Russian and Ukrainian Nuclear Power Plants (NPPs). Pacific Northwest National Laboratory (PNNL) and Brookhaven National Laboratory (BNL) manage and provide technical oversight of the various INSP simulator projects for DOE. The program also includes a simulator technology transfer process to simulator design organizations in Russia and Ukraine. Training programs, installation of new simulators, and enhancements in existing simulators, are viewed as providing a relatively fast and cost-effective technology transfer that will result in measurable improvement in the safety culture and operation of NPPs. A review of this program, its present status, and its accomplishments are provided in this paper

Planning a revolution in nuclear power technology

International Nuclear Information System (INIS)

Egan, J.R.

1987-01-01

Approaching the marketing and deployment of small, inherently safe reactors from the standpoint of the legal and financial community, the author suggests various ideal planning criteria that should be adhered to by designers and suppliers in order for the new plants to achieve political and financial acceptability. Although new nuclear technology based on those criteria promise to rekindle the prospects for nuclear fission, neither governments nor suppliers are likely to undertake the requisite investments. Rather, the author proposes a private development initiative between the political community, private investors, and would-be suppliers. (author)

Nuclear medicine technology study guide

CERN Document Server

Patel, Dee

2011-01-01

Nuclear Medicine Technology Study Guide presents a comprehensive review of nuclear medicine principles and concepts necessary for technologists to pass board examinations. The practice questions and content follow the guidelines of the Nuclear Medicine Technology Certification Board (NMTCB) and American Registry of Radiological Technologists (ARRT), allowing test takers to maximize their success in passing the examinations. The book is organized by sections of increasing difficulty, with over 600 multiple-choice questions covering all areas of nuclear medicine, including radiation safety; radi

Development of MMIS design technology for integral reactor

International Nuclear Information System (INIS)

Koo, In Soo; Park, H. Y.; Park, G. O.

2002-03-01

Man-Machine Interface Systems (MMIS) are composed of the control room related to plant operations and the Instrumentation and Control (I and C) including functions such as plant protections, plant controls and monitoring. The applications of the advanced concepts and the digital technologies are required to reduce events due to human fails clarified existing nuclear power plants, and enhance reliability and safety of the I and C equipment. The development of MMIS technologies and the establishment of the MMIS basic design package are required to enhance the completeness of the MMIS design. The purpose of the MMIS development is to provide the assurance of the conceptual design based on the architecture and the concepts of MMIS during the first development stage, to establish the design technology of MMIS and to provide the design process for the detailed design. The products of SMART MMIS development such as the system design requirements, the interface requirements and system descriptions will be used to the detail design of the SMART MMIS. Those area will be the implementation of the I and C systems such as information processing system, alarms and indications systems, protection systems, control systems and data communication networks, and the MMI facilities such as main control room, remote shutdown panel and emergency operation facilities. When the prototype testing of I and C systems and the mock-up experiment of MMI facilities are performed, the whole MMIS package will be installed in the nuclear power plants including SMART

Nuclear technology

International Nuclear Information System (INIS)

1983-03-01

This report examines nuclear technology in Canada, with emphasis on Quebec, as a means of revitilizing industry. The historical, present day, and future states of Atomic Energy of Canada Limited are examined. Future research programs are discussed in greatest detail. These range from disposal of porcine wastes to new applications for electricity to nuclear medical techniques (to cite only a few examples). The executive summary is written in English. (23 fig., 16 tab.)

Analysis on the status of the application of satellite remote sensing technology to nuclear safeguards

International Nuclear Information System (INIS)

Tao Zhangsheng; Zhao Yingjun

2008-01-01

Based on the application status of satellite remote sensing technology to nuclear safeguards, advantage of satellite remote sensing technology is analyzed, main types of satellite image used in nuclear safeguards are elaborated and the main application of satellite images is regarded to detect, verify and monitor nuclear activities; verify additional protocol declaration and design information, support performing complementary access inspections; investigate alleged undeclared activities based on open source or the third party information. Application examples of satellite image in nuclear safeguards to analyze nuclear facilities by other countries, the ability of remote sensing technology in nuclear safeguards is discussed. (authors)

Experience in transfer of nuclear technology

International Nuclear Information System (INIS)

Beckurts, K.H.

1977-01-01

Nuclear energy development in the Federal Republic of Germany was initiated in 1955. In spite of this late start, the country now has a broad potential in all branches of peaceful nuclear technology. Turkey nuclear power plants are erected by German industry, and the country has the basic technology at its disposal for all stages of the nuclear fuel cycle. In the areas of uranium enrichment and reprocessing, multilateral joint ventures with European countries have been formed. The country also has an active development program for advanced reactors. In general areas of technology transfer and development aid, in the nuclear field, there are interrelated activities of both government and industry. The government has concluded bilateral agreements with a number of countires e.g. Argentina, Brazil, India, Iran and Pakistan, covering the general field of nuclear science; in the framework of these agreements, which are being carried out mainly by the nuclear research centers at Juelich and Karlsruhe, active cooperation in research, development, education, and training are being pursued. The nonproliferation of nuclear weapons is a major objective of the Federal government which strongly affects its policies for international nuclear trade. The paper describes the nuclear technology potential available in the Federal Republic of Germany and reviews experience gathered in cooperation with developing countries. Future policies for nuclear technology transfer are discussed with special reference to the role of national R and D laboratories

The status and prospects of nuclear reactor technology development

International Nuclear Information System (INIS)

Juhn, P.E.

2001-01-01

Nuclear power is a proven technology which currently contributes about 16% to the world electricity supply and, to a much lesser extent, to heat supply in some countries. Nuclear Power is economically competitive with fossil fuels for base load electricity generation in many countries, and is one of the commercially proven energy supply options that could be extended in the future to reduce environmental burdens, especially greenhouse gas emissions, from the electricity sector. Over the past five decades, nearly ten thousand reactor-years of operating experience have been accumulated with current nuclear power plants. However, nuclear power is currently at a cross-road. There are no new nuclear power construction projects in most parts of the world, except some countries in East Asia and Eastern Europe. The main issues are economic competitiveness with cheap gas plants and public concerns on nuclear waste disposal and safety. Strong economic growth and the shrinking of existing electricity over-capacities could favour nuclear power. Since nuclear power emits no greenhouse gases to the environment, its development could be further accelerated by a breakthrough in innovative nuclear reactor technology development. Great attention also needs to be paid to the design of new nuclear reactors, which are modularized and faster to construct, thus reducing capital investment and construction period, and thereby improving their overall economics and their compatibility with the infrastructure of, in particular, developing countries, where new energy demands are expected. This paper discusses the future world energy outlook, challenges for and progresses on nuclear power; overview of new nuclear reactor technology development; and the role of the International Atomic Energy Agency (IAEA) in the development of new innovative nuclear reactors. (author)

The development of nuclear technology transfer

International Nuclear Information System (INIS)

Nack-chung Sung

1987-01-01

Korea, as a recipient of nuclear technology transfer, has good experience of progressively building up its indigeneous capability of nuclear technology through three stages of technology transfer, namely: technology transfer under the turnkey approach, component approach, and integrated technology transfer with a local prime contractor. Here, each stage of experience of technology transfer, with Korea as a recipient, is presented. (author)

Transferring nuclear power technology to foster Chinese self-reliance

International Nuclear Information System (INIS)

Levi, J-D.

1998-01-01

Being convinced that nuclear energy will play an important role in meeting its huge future energy demands, China considers that the development of a very strong national nuclear industry capable of covering all aspects of a major national power program is of paramount importance.In this context, China has invited its foreign partners to propose contributions to the studies for this development, in view of establishing a suitable cooperation program with the entire Chinese nuclear power industry, including design institutes, equipment manufacturers, construction companies and plant operators.One of the main objectives defined by the Chinese authorities for the further development of their nuclear industry with some international cooperation is the achievement of a very high level of self-reliance by Chinese industry in all of the following areas: project management, design and engineering, construction, equipment design and manufacturing,operation and maintenance. The major key to reaching this target of overall and long term self reliance lies in the implementation of thorough design know how transfer towards all partners of the Chinese nuclear industry, who shall acquire the necessary capabilities so as to completely master nuclear engineering. While this policy might entail fairly high front end investments by the technology receivers, in terms of industrial infrastructure nad engineering capabilities it is expected to pay off over the long term with the development of a substantial nuclear power plant construction program.(DM)

Contributions to nuclear safety and radiation technologies in Ukraine by the Science and Technology Center in Ukraine (STCU)

International Nuclear Information System (INIS)

Taranenko, L.; Janouch, F.; Owsiacki, L.

2001-01-01

This paper presents Science and Technology Center in Ukraine (STCU) activities devoted to furthering nuclear and radiation safety, which is a prioritized STCU area. The STCU, an intergovernmental organization with the principle objective of non-proliferation, administers financial support from the USA, Canada, and the EU to Ukrainian projects in various scientific and technological areas; coordinates projects; and promotes the integration of Ukrainian scientists into the international scientific community, including involving western collaborators. The paper focuses on STCU's largest project to date 'Program Supporting Y2K Readiness at Ukrainian NPPs' initiated in April 1999 and designed to address possible Y2K readiness problems at 14 Ukrainian nuclear reactors. Other presented projects demonstrate a wide diversity of supported directions in the fields of nuclear and radiation safety, including reactor material improvement ('Improved Zirconium-Based Elements for Nuclear Reactors'), information technologies for nuclear industries ('Ukrainian Nuclear Data Bank in Slavutich'), and radiation health science ('Diagnostics and Treatment of Radiation-Induced Injuries of Human Biopolymers').

Science and nuclear technology communication in Cordoba

International Nuclear Information System (INIS)

Martin, Hugo R.

2012-01-01

This paper describes the communication activities conducted nuclear science and technology in 2012 in the scientific, educational and tourist areas of Cordoba. The first is the Promotion of the realization of scientific research school works to present in science and technology fairs. The public exhibitions fairs consist of projects conducted by students from all levels of the education system. To do this, students have the guidance of Advisory Teachers, researchers and technologists of the local scientific community, which involves training them for a period of approximately six months. During this year the courses were conducted in 37 cities in the interior province, which are the sites of Regional Headquarters, which included the promotion of the realization of school scientific research on the peaceful applications of nuclear technology and / or national nuclear activities. During the meetings, made presentations basing pedagogical and didactic aspects to coordination between teaching of conceptual content and activities practical introduction to nuclear scientific methodology. As a result of this initiative, between the months of June and September was reached more than 3,000 teachers, using the infrastructure of the Ministry of Science and Technology and Internet. As a result, a dozen schools have begun to seek assistance to develop projects related to nuclear power. Other activities under the name of Scientific School Research Incursion through Experiences with Natural Radiation, consisted of the design and realization of simple laboratory experiences in laboratory's schools. The objective was to strengthen the curriculum and promote critical thinking about the risks and benefits of nuclear technologies in relation to exposure to ionizing radiation involving them. As a result it has been observed that these activities contribute to a progressive scientific and technological literacy of students, who build original knowledge for themselves and develop

Canadian Experience in Nuclear Power Technology Transfer

International Nuclear Information System (INIS)

Boulton, J.

1987-01-01

Technology transfer has and will continue to play a major role in the development of nuclear power programs. From the early beginnings of the development of the peaceful uses of nuclear power by just a few nations in the mid-1940s there has been a considerable transfer of technology and today 34 countries have nuclear programs in various stages of development. Indeed, some of the major nuclear vendors achieves their present position through a process of technology transfer and subsequent development. Canada, one of the early leaders in the development of nuclear power, has experience with a wide range of programs bout within its own borders and with other countries. This paper briefly describes this experience and the lessons learned from Canada's involvement in the transfer of nuclear power technology. Nuclear technology is complex and diverse and yet it can be assimilated by a nation given a fire commitment of both suppliers and recipients of technology to achieve success. Canada has reaped large benefits from its nuclear program and we believe this has been instrumentally linked to the sharing of goals and opportunity for participation over extended periods of time by many interests within the Canadian infrastructure. While Canada has accumulated considerable expertise in nuclear technology transfer, we believe there is still much for US to learn. Achieving proficiency in any of the many kinds of nuclear related technologies will place a heavy burden on the financial and human resources of a nation. Care must be taken to plan carefully the total criteria which will assure national benefits in industrial and economic development. Above all, effective transfer of nuclear technology requires a long term commitment by both parties

An AI-based layout design system for nuclear power plants

International Nuclear Information System (INIS)

Fujita, Kikuo; Akagi, Shinsuke; Nakatogawa, Tetsundo; Tanaka, Kazuo; Takeuchi, Makoto.

1991-01-01

An AI-based layout design system for nuclear power plants has been developed. The design of the layout of nuclear power plants is a time-consuming task requiring expertise, in which a lot of machinery and equipment must be arranged in a plant building considering various kinds of design constraints, i.e. spatial, functional, economical etc. Computer aided layout design systems have been widely expected and the application of AI technology is expected as a promising approach for the synthesis phase of this task. In this paper, we present an approach to the layout design of nuclear power plants based on a constraint-directed search; one of the AI techniques. In addition, we show how it was implemented with an object-oriented programming technique and give an example of its application. (author)

Practice and exploration: build nuclear science and technology information resources management system based on the TRS platform

International Nuclear Information System (INIS)

Huang Jing; Meng Xu

2010-01-01

Nuclear science and technology information has played a very important role in the development of Chinese nuclear industry. In information explosion and information technology swift development's today, how to use information technology method to management and shared the nuclear information of nuclear research institutes, nuclear power plants and other nuclear-related units, become an important subject of nuclear information work. TRS information resource management platform provide a doable solution to manage and share the nuclear science and technology information. Nuclear Power Institute of China has built a nuclear science and technology information resources management system based on the TRS platform, through some steps just like system design, re-development and resource building. This management system has served for the research, testing, production and operation. (authors)

Experience-based innovations in management of nuclear power plant technology

International Nuclear Information System (INIS)

Wagner, R.L.; Bradbury, R.B.; Freeman, D.V.; Jacobs, S.B.

1987-01-01

During 45 years of nuclear technology development and experience, Stone and Webster (S and W) has developed and successfully applied various innovative techniques to numerous nuclear projects. These techniques, developed primarily in response to the increasing scope and complexity of nuclear power plants, have been used and refined to provide efficient management of the two major nuclear project acticities-design and construction. For this paper, these techniques have been divided into: 1) engineering-based innovations, 2) construction-based innovations, and 3) management-based innovations. (author)

Experience-based innovations in management of nuclear power plant technology

International Nuclear Information System (INIS)

Wagner, R.L.; Bradbury, R.B.; Freeman, D.V.; Jacobs, S.B.

1988-01-01

During 45 years of nuclear technology development and experience, Stone and Webster (S and W) has developed and successfully applied various innovative techniques to numerous nuclear projects. These techniques, developed primarily in response to the increasing scope and complexity of nuclear power plants, have been used and refined to provide efficient management of the two major nuclear project activities - design and construction. For this paper, these techniques have been divided into: (1) engineering-based innovations, (2) construction-based innovations, and (3) management-based innovations

Status and trends of nuclear technologies - Report of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

International Nuclear Information System (INIS)

2009-09-01

The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was launched in the year 2000, based on a resolution by the IAEA General Conference (GC(44)/RES/21). INPRO intends to help to ensure that nuclear energy is available in the 21st century in a sustainable manner, and seeks to bring together all interested Member States, both technology holders and technology users, to consider, jointly, actions to achieve desired innovations. INPRO is taking care of the specific needs of developing countries. This IAEA publication is part of Phase 1 of INPRO. It intends to provide an overview on history, present situation and future perspectives of nuclear fuel cycle technologies. While this overview focuses on technical issues, nevertheless, the aspects of economics, environment, and safety and proliferation resistance are important background issues for this study. After a brief description about the INPRO project and an evaluation of existing and future reactor designs the publication covers nuclear fuel cycle issues in detail. It is expected that this documentation will provide IAEA Member States and their nuclear engineers and designers, as well as policy makers with useful information on status and trends of future nuclear fuel cycle technologies. Due to the size of the full report it was decided to create a summary of the information and attach a CD-ROM in the back of this summary report with the full text of the report

4'' + D VR technology for structural analysis and integrated maintenance of nuclear power plants

International Nuclear Information System (INIS)

Lee, I. S.; Yoon, S. H.; Shim, K. W.; Yu, Y. H.; Suh, K. Y.

2002-01-01

There continues to be an increasing demand of electricity around the globe to fuel the industrial growth and to promote the human welfare. The economic activities have brought about richness in our material and cultural lives, in which process the electric power has been at the heart of the versatile energy sources. In order to timely and competitively respond to rapidly changing energy environment in the twenty-first century there is a growing need to build the advanced nuclear power plants in the unlimited K, which were confirmed by FTIR and 51 V Ncommissioning. One can then realistically evaluate their construction time and cost per varying methods and options available from the leading-edge technology. In particular a great deal of efforts have yet to be made for time- and cost-dependent plant simulation and dynamically coupled database construction in the VR space. The operator training and personnel education may also benefit from the VR technology. The present work is being proposed in the three-dimensional space and time plus cost coordinates, i.e. four plus dimensional (4 + D) coordinates. The 4 + D VR application will enable the nuclear industry to narrow the technological gap from the other leading industries that have long since been employing the VR engineering. The 4 + D technology will help nurture public understanding of the special discipline of nuclear power plants. The technology will also facilitate public access to the knowledge on the nuclear science and engineering which has so far been monopolized by the academia, national laboratories and the heavy industry. The 4 + D virtual design and construction will open up the new horizon for revitalization of the nuclear industry over the globe in the foreseeable future. Considering the long construction and operation time for the nuclear power plants, the preliminary VR simulation capability for the plants will supply the vital information not only for the actual design and construction of the

The research and implementation of nuclear science and technology literature processing system based on smart client technology

International Nuclear Information System (INIS)

Zhang Shufeng

2010-01-01

Nuclear literature processing, namely cataloging, subject indexing and abstracting, is one of the highly specialized work, the quality and speed of literature processing have an important impact on the building of information resources in nuclear field. Firstly, the system's overall functionality was determined through the analysis of system requirements and the difficulties we meet with were pointed out. Secondly, the function of collaborative collecting and processing of nuclear literature is realized using smart client technology, achieve the purpose of providing a network platform to the literature processing specialists located in different places, therefore the out source of nuclear literature collecting and processing can be done. The article comprises three aspects: needs analysis and overall functional design, smart client technical presentations, Net platform based on smart client technology, nuclear literature processing system implementation. (author)

Development of core design and analyses technology for integral reactor

Energy Technology Data Exchange (ETDEWEB)

Zee, Sung Quun; Lee, C. C.; Song, J. S. and others

1999-03-01

Integral reactors are developed for the applications such as sea water desalination, heat energy for various industries, and power sources for large container ships. In order to enhance the inherent and passive safety features, low power density concept is chosen for the integral reactor SMART. Moreover, ultra-longer cycle and boron-free operation concepts are reviewed for better plant economy and simple design of reactor system. Especially, boron-free operation concept brings about large difference in core configurations and reactivity controls from those of the existing large size commercial nuclear power plants and also causes many differences in the safety aspects. The ultimate objectives of this study include detailed core design of a integral reactor, development of the core design system and technology, and finally acquisition of the system design certificate. The goal of the first stage is the conceptual core design, that is, to establish the design bases and requirements suitable for the boron-free concept, to develop a core loading pattern, to analyze the nuclear, thermal and hydraulic characteristics of the core and to perform the core shielding design. Interface data for safety and performance analyses including fuel design data are produced for the relevant design analysis groups. Nuclear, thermal and hydraulic, shielding design and analysis code systems necessary for the core conceptual design are established through modification of the existing design tools and newly developed methodology and code modules. Core safety and performance can be improved by the technology development such as boron-free core optimization, advaned core monitoring and operational aid system. Feasiblity study on the improvement of the core protection and monitoring system will also contribute toward core safety and performance. Both the conceptual core design study and the related technology will provide concrete basis for the next design phase. This study will also

Development of core design and analyses technology for integral reactor

International Nuclear Information System (INIS)

Zee, Sung Quun; Lee, C. C.; Song, J. S. and others

1999-03-01

Integral reactors are developed for the applications such as sea water desalination, heat energy for various industries, and power sources for large container ships. In order to enhance the inherent and passive safety features, low power density concept is chosen for the integral reactor SMART. Moreover, ultra-longer cycle and boron-free operation concepts are reviewed for better plant economy and simple design of reactor system. Especially, boron-free operation concept brings about large difference in core configurations and reactivity controls from those of the existing large size commercial nuclear power plants and also causes many differences in the safety aspects. The ultimate objectives of this study include detailed core design of a integral reactor, development of the core design system and technology, and finally acquisition of the system design certificate. The goal of the first stage is the conceptual core design, that is, to establish the design bases and requirements suitable for the boron-free concept, to develop a core loading pattern, to analyze the nuclear, thermal and hydraulic characteristics of the core and to perform the core shielding design. Interface data for safety and performance analyses including fuel design data are produced for the relevant design analysis groups. Nuclear, thermal and hydraulic, shielding design and analysis code systems necessary for the core conceptual design are established through modification of the existing design tools and newly developed methodology and code modules. Core safety and performance can be improved by the technology development such as boron-free core optimization, advaned core monitoring and operational aid system. Feasiblity study on the improvement of the core protection and monitoring system will also contribute toward core safety and performance. Both the conceptual core design study and the related technology will provide concrete basis for the next design phase. This study will also

Analysis of effect of safety classification on DCS design in nuclear power plants

International Nuclear Information System (INIS)

Gou Guokai; Li Guomin; Wang Qunfeng

2011-01-01

By analyzing the safety classification for the systems and functions of nuclear power plants based on the general design requirements for nuclear power plants, especially the requirement of availability and reliability of I and C systems, the characteristics of modem DCS technology and I and C products currently applied in nuclear power field are interpreted. According to the requirements on the safety operation of nuclear power plants and the regulations for safety audit, the effect of different safety classifications on DCS design in nuclear power plants is analyzed, by considering the actual design process of different DCS solutions in the nuclear power plants under construction. (authors)

NASA's nuclear thermal propulsion technology project

International Nuclear Information System (INIS)

Peecook, K.M.; Stone, J.R.

1992-07-01

The nonnuclear subsystem technologies required for incorporating nuclear thermal propulsion (NTP) into space-exploration missions are discussed. Of particular interest to planned missions are such technologies as materials, instrumentation and controls, turbomachinery, CFD modeling, nozzle extension designs and models, and analyses of exhaust plumes. NASA studies are described and/or proposed for refractory metals and alloys, robotic NTP controls, and turbopump materials candidates. Alternative nozzle concepts such as aerospikes and truncated plugs are proposed, and numerical simulations are set forth for studying heavy molecules and the backstreaming of highly reactive free-radical hydrogen in the exhaust plume. The critical technologies described in the paper are central to the development of NTP, and NTP has the potential to facilitate a range of space exploration activities. 3 refs

Review of revised Japanese seismic guidelines for Nuclear Power Plant design

International Nuclear Information System (INIS)

Kato, M.

1987-01-01

Development of aseismic design for nuclear power plants in Japan has evolved roughly in three stages. The first phase, which continued by 1978, was a period progressive development when design for each siteplant has referred to designs of predecessor plants and have added the latest knowledge and experience in that time. The second phase from issuance of 'Regulatory Guide for Aseismic Design of Nuclear Power Reactor Facilities' (1978, revised in 1981), or 1978 to 1986, was a period when the application of customary conservative design method was continued, while standardization of the aseismic design technology have been proceded. It is in this phase when new knowledge was accumulated by aseismic proof studies. The third phase represents a transient period to rational design when the conservative aseismic design technology has been reviewed due to the new knowledge and revision of the above JEAG guideline has progressed for incorporation in design, and ont the other hand by-laws of the Ministry of International Trade and Industry are being provided. In this report a review is given of aseismic design and its guideline after the second phase onward and an overview of the revised JEAG - Recent Aseismic Design Method - and the by-laws including rationalization of aseismic design technology

Fusion of Nuclear and Emerging Technology

International Nuclear Information System (INIS)

Nahrul Khaer Alang Rashid

2005-04-01

The presentation discussed the following subjects: emerging technology; nuclear technology; fusion emerging and nuclear technology; progressive nature of knowledge; optically stimulated luminescence - application of luminescence technology to sediments; Biosystemics technology -convergence nanotechnology, ecological science, biotechnology, cognitive science and IT - prospective impact on materials science, the management of public system for bio-health, eco and food system integrity and disease mitigation

Summary of Survey and Workshop Results on Areas of Research in Human Factors for the Design and Operation of New Nuclear Plant Technology - Final Report

International Nuclear Information System (INIS)

Persensky, Julius J.; Joe, Jeffrey; Richards, Robert E.; Barnes, Valerie; Gonzalez, Michelle

2012-01-01

The nuclear community is currently at a stage where existing reactor control stations are undergoing various forms of modernization, new reactors are being built in many countries with computer-based control rooms, and advanced reactors are being designed through international cooperation to support power generation for decades to come. With the introduction of advanced plants, we will see new reactor and system designs, new tools to support plant personnel, and changes to nuclear power plant (NPP) staffing configurations. The concepts of operation and maintenance for this new generation of plants are likely to be quite different from those employed in today's plants. It is important that the potential impact of these developments is evaluated and understood by prospective operators and regulators responsible for determining the acceptability of new designs to support human performance in maintaining plant safety. The introduction of new technology is viewed as having promise for improving the safe and efficient operation of NPPs. To ensure the appropriate application of technology to support human performance and plant safety, it is important to evaluate the technological advances in terms of both potential negative and positive effects. Research described in this paper can provide the technical basis to help ensure that the benefits of new technology are realized and that the potential negative effects are minimized. The impetus for the current effort grew out of a Nuclear Energy Agency, Committee on the Safety of Nuclear Installations, Working Group on Human and Organizational Factors, Technical Opinion Paper (TOP) titled, 'Research on Human Factors in New Nuclear Plant Technology' [NEA/CSNI/R(2009)7], which identified eight broad topic areas that warrant further research: 1. Operating Experience (OpEx) from New and Modernized Plants. 2. Evolving Concepts for the Operation of Nuclear Power Plants. 3. The Role of Automation and Personnel: New Concepts of Teamwork

Innovation Priorities in Nuclear and Radiation Technologies in Russia. View from Skolkovo

International Nuclear Information System (INIS)

Fertman, A.; Kovalevich, D.; Turtikov, V.; Zaytseva, N.

2012-01-01

The direction for the modernization and technological development of 'Nuclear Technologies' sector of the Russian economy comprises a group of scientific and engineering subjects (atomic engineering, technologies on the basis of radiation, change of properties of materials, radiation resistant microelectronics, etc.), and serves as the foundation of one of the most high-tech industries. The innovative development of nuclear technologies is an integral condition for the strengthening (and in some directions of conquering) a country's position as a global technological leader and preservation of defensive capability of the nation. For this reason, nuclear technologies became one of the priority areas for the activity of the Skolkovo Center. The wide opportunities offered by the application of nuclear technologies were already clear at the deployment stage of the 'Nuclear Project - 1'. In 1958, at the 2nd International conference on the peaceful use of nuclear energy in Geneva, the USSR presented more than 200 reports and communiques in all civil use of atomic energy directions.One of the major results of the development of the nuclear branch have become the developments in the sphere of control of radiation and magnetic fields (radiation technologies). This group of technologies have actively developed in collaboration with design and manufacturing of different types of equipment, including accelerators, neutron generators, lasers, HF-systems, detectors of particles and radiation, microscopes and telescopes, microwave microelectronics, etc. Today these technologies and equipment are used in a variety of other (non-power and not military) markets - and the list of these markets grows constantly. Among the fastest growing ones, we can list the markets of nuclear medicine, sterilization and disinfection, safety and non-destructive testing, ecology and water processing, extraction and the processing of minerals. Historically, the development of nuclear technologies

Development of technology for next generation reactor - Research of evaluation technology for nuclear power plant -

Energy Technology Data Exchange (ETDEWEB)

Park, Jong Kyun; Chang, Moon Heuy; Hwang, Yung Dong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)] [and others

1993-09-01

For development of next generation reactor, a project for evaluation technology for nuclear power plant is performed. Evaluation technology is essential to next generation reactor for reactor safety and system analysis. For design concept, detailed evaluation technologies are studied as follows: evaluation of safety margin, evaluation of safety facilities, evaluation of measurement and control technology; man-machine interface. Especially for thermal efficiency, thermal properties and chemical composition of inconel 690 tube, instead of inconel 600 tube, are measured for steam generator. (Author).

ANSTO: Australian Nuclear Science and Technology Organization

International Nuclear Information System (INIS)

1989-01-01

The Australian Nuclear Science and Technology Organization conducts or is engaged in collaborative research and development in the application of nuclear science and associated technology. Through its Australian radio-isotopes unit, it markets radioisotopes, their products and other services for nuclear medicine industry and research. It also operates national nuclear facilities ( HIFAR and Moata research reactors), promote training, provide advice and disseminates information on nuclear science and technology. The booklet briefly outlines these activities. ills

A Unique Master's Program in Combined Nuclear Technology and Nuclear Chemistry at Chalmers University of Technology, Sweden

International Nuclear Information System (INIS)

Skarnemark, Gunnar; Allard, Stefan; Ekberg, Christian; Nordlund, Anders

2009-01-01

The need for engineers and scientists who can ensure safe and secure use of nuclear energy is large in Sweden and internationally. Chalmers University of Technology is therefore launching a new 2-year master's program in Nuclear Engineering, with start from the autumn of 2009. The program is open to Swedish and foreign students. The program starts with compulsory courses dealing with the basics of nuclear chemistry and physics, radiation protection, nuclear power and reactors, nuclear fuel supply, nuclear waste management and nuclear safety and security. There are also compulsory courses in nuclear industry applications and sustainable energy futures. The subsequent elective courses can be chosen freely but there is also a possibility to choose informal tracks that concentrate on nuclear chemistry or reactor technology and physics. The nuclear chemistry track comprises courses in e.g. chemistry of lanthanides, actinides and transactinides, solvent extraction, radioecology and radioanalytical chemistry and radiopharmaceuticals. The program is finished with a one semester thesis project. This is probably a unique master program in the sense of its combination of deep courses in both nuclear technology and nuclear chemistry.

Nuclear Reactors and Technology; (USA)

Energy Technology Data Exchange (ETDEWEB)

Cason, D.L.; Hicks, S.C. (eds.)

1991-01-01

Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database (EDB) during the past month. Also included are US information obtained through acquisition programs or interagency agreements and international information obtained through the International Energy Agency's Energy Technology Data Exchange or government-to-government agreements. The digests in NRT and other citations to information on nuclear reactors back to 1948 are available for online searching and retrieval on EDB and Nuclear Science Abstracts (NSA) database. Current information, added daily to EDB, is available to DOE and its contractors through the DOE integrated Technical Information System. Customized profiles can be developed to provide current information to meet each user's needs.

A study on nuclear technology policy

International Nuclear Information System (INIS)

Kim, H. J.; Oh, K. B.; Lee, K. S.; Chung, W. S.; Lee, T. J.; Yun, S. W.; Jeong, I.

2004-01-01

This study was conducted as a part of institutional activities of KAERI, and the objective of the study is to survey and analyze the change of international environment in nuclear use and research and development environment, and to propose systematic alternatives on technology policy for efficiency and effectiveness of research and development through national R and D program while timely responding to the environmental change in local and global sense. Acknowledging the importance of the relationship between the external environment and the national nuclear R and D strategic planning, this study focused on the two major subjects: (1) the international environmental and technological change attached to the development of nuclear power; (2) the direction and strategy of nuclear R and D to improve effectiveness through national R and D programs as role of electricity in the future society, strategic environment of nuclear use and R and D in the future society, energy environment and nuclear technology development scenario in the future, strategic study on future vision of KAERI and technological road-mapping of national nuclear R and D for enhancing competitiveness

Cryogenics in nuclear reactor technology

International Nuclear Information System (INIS)

Dharmadurai, G.

1982-01-01

The cryogenic technology has significantly contributed to the development of several proven techniques for use in the nuclear power industry. A noteworthy feature is the unique role of cryogenics in minimising the release of radioactive and some chemical pollutants to the environment during the operation of various plants associated with this industry. The salient technological features of several cryogenic processes relevant to the nuclear reactor technology are discussed. (author)

The civil design of the Angra Nuclear power plant, units 2 and 3

International Nuclear Information System (INIS)

Zuegel, L.C.; Diaz, B.E.; Cunha, M.T.

1988-01-01

The civil design of the Angra Nuclear Power Plant, Units 2 and 3 represents an important step in the technological development of Brazil, correlated to high technology enterprises. This design was developed in Brazil, by Brazilian technicians, in a comprehensive way. In all individual and global phases of the design, a full participation of the Brazilian state and private companies has been observed. In order to proceed with the design in this way, a group of Nuclen engineers has stayed for a while in Germany, in KWU's office, for a proper training. The Brazilian design companies, on the other hand, have received a special consulting support given by engineers of German construction companies, especialized in nuclear power plant construction. For the nuclear civil design, as well as for the dynamic analyses and structural design of reinforced concrete and steel structures, the design job assumes an important position in the Brazilian technical experience. The structural design of the reinforced concrete structures of the nuclear power plant, for instance, is the largest one ever performed in Brazil in terms of difficulty, complexity and amount of man-hours expediture. A summary of the civil design steps will be described in this paper. (author) [pt

Socio-technological study for establishing comprehensive nuclear safety system

International Nuclear Information System (INIS)

Furuta, Kazuo; Kanno, Taro; Yagi, Ekou; Shuto, Yuki

2003-01-01

This paper presents an overview and preliminary results of a research project on social-technology for nuclear safety, which started in October 2001. In particular, emergency response preparedness against nuclear disaster and consensus development will be discussed. The architecture of an emergency response simulator will be given, which is for assessing design of disaster prevention systems. A conceptual model of evacuation behavior of a resident has been constructed from analysis of past disaster cases. As for consensus development, deliberation spaces of actual committee meetings were constructed by analyzing transcripts of the meetings based on an opinion schema. A model of consensus development process has been proposed from the traces of participants' opinions over the deliberation spaces. Such a socio-technological approach will be useful not only for nuclear safety but also for safety of non-nuclear domains and human activities of a high hazard potential; it is expected to contribute to establishing risk-aware society of the future. (author)

Using New Technologies for Design, Modernization and Automation of Systems and Processes Related with Nuclear Applications. Technical Report of an Experts' Meeting

International Nuclear Information System (INIS)

2016-04-01

In recent years the International Atomic Energy Agency has organized a series of technical cooperation projects aimed at expanding and strengthening the capacities of laboratories that work with nuclear instrumentation, as well as developing prototypes of instruments and interfaces which can respond to different needs in nuclear applications in the Latin America Caribbean (RLA) region. The introduction of advanced technologies for the design of instrumentation, interfaces and devices specialized and for work automation systems or processes related nuclear applications, has enabled to make better use of the available instrumentation. Repair work and modernization are an alternative to counter the lack of maintenance services by equipment suppliers that exceed the time life provided by manufacturers (planned obsolescence). Not only do specialized designs allow to solve specific needs, but often help reduce costs and the deadlines of work. An expert' meeting was held under the regional project RLA1011 (Support Automation Systems and Processes in Nuclear Facilities) to prepare a technical report that would provide recommendations to Member States of the IAEA on the current state of development several advanced technologies and their main fields of application, including examples of work in the region within the framework of this project. Eleven analytics entirely in Spanish from participating Member States are included in this publication

International conference on innovative technologies for nuclear fuel cycles and nuclear power. Unedited proceedings

International Nuclear Information System (INIS)

2004-01-01

technology is considered to have matured as an industry, innovation is foreseen for further improvement of safety, economy, sustainability, non-proliferation, etc. On the other hand, the general public, politicians and environmental Non Governmental Organizations (NGO's) in many countries view nuclear specialists with distrust. In their view nuclear energy is not needed in the short and medium term and likely not also in the long term. Innovative fuel cycles and nuclear power technologies have to achieve inherent safety, proliferation resistance, foolproof measures against terrorist acts and sabotage, etc., even for being considered as an option. Thus there is a gap to be bridged if the potential benefits of nuclear energy are to be realized for peace and prosperity of humanity. Technical measures such as well-defined user requirements, improved design concepts and applications in addition to electricity generation, have to be developed. Communication has to be substantially improved both within the nuclear community and with the public and society at large. Apart from achieving acceptable economic targets in terms of cost per installed kilowatt and investment cost, it would be necessary to seek appropriate solutions for improving the investment attractiveness of nuclear plants in developing countries. The conference succeeded in bringing together top managers, policy makers and specialists from developed and developing countries as well as representatives of R and D activities in Member States and international projects. There was a broad agreement amongst the participants that international collaboration in general and the collaboration especially between Gen IV and INPRO initiatives should be improved and substantially expanded. The IAEA is expected by all to play a key role in coordinating international efforts to develop innovative technologies

Development Trends in Nuclear Technology and Related Safety Aspects

International Nuclear Information System (INIS)

Kuczera, B.; Juhn, P.E.; Fukuda, K.

2002-01-01

The IAEA Safety Standards Series include, in a hierarchical manner, the categories of Safety Fundamentals, Safety Requirements and Safety Guides, which define the elements necessary to ensure the safety of nuclear installations. In the same way as nuclear technology and scientific knowledge advance continuously, also safety requirements may change with these advances. Therefore, in the framework of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) one important aspect among others refers to user requirements on the safety of innovative nuclear installations, which may come into operation within the next fifty years. In this respect, the major objectives of the INPRO sub-task 'User Requirements and Nuclear Energy Development Criteria in the Area of Safety' have been: a. to overview existing national and international requirements in the safety area, b. to define high level user requirements in the area of safety of innovative nuclear technologies, c. to compile and to analyze existing innovative reactor and fuel cycle technology enhancement concepts and approaches intended to achieve a high degree of safety, and d. to identify the general areas of safety R and D needs for the establishment of these technologies. During the discussions it became evident that the application of the defence in depth strategy will continue to be the overriding approach for achieving the general safety objective in nuclear power plants and fuel cycle facilities, where the emphasis will be shifted from mitigation of accident consequences more towards prevention of accidents. In this context, four high level user requirements have been formulated for the safety of innovative nuclear reactors and fuel cycles. On this basis safety strategies for innovative reactor designs are highlighted in each of the five levels of defence in depth and specific requirements are discussed for the individual components of the fuel cycle. (authors)

AREVA Germany. International competence in nuclear technology

International Nuclear Information System (INIS)

Graeber, Ulrich

2011-01-01

AREVA NP was created in 2001 by the merger of the French nuclear technology specialist Framatome with the nuclear sector of Siemens. The company is headquartered in Paris and has regional subsidiaries in Germany and the United States. The joint venture's strength lies in its all-round competence in nuclear power plants, from reactor development to power plant services and modernization of operating plants, design and production of fuel assemblies and turn-key construction of nuclear power reactors. Major core competences are located in Germany including the test facilities which are unique in the entire group as well as electrical engineering and instrumentation and control systems. AREVA NP is part of the globally acting AREVA group which pursues a unique integrated business model. The concept covers the entire nuclear fuel cycle from uranium mining to reprocessing used fuel assemblies. At present, AREVA has 48,000 employees worldwide, of which 5,700 are Germany-based. (orig.)

China's nuclear technology for economy growth

International Nuclear Information System (INIS)

Lu, Yanxiao

1998-01-01

The transfer of nuclear technology to practical applications in energy, agriculture, food, industries and others has made important contributions to the prosperity of the national economy and the improvement of living standard of Chinese people in the past 40 years. Facing the great challenges in upcoming years, sustained efforts are needed to promote industrialization, commercialization and internationalization of nuclear technology. Rapid economic growth is providing the golden opportunities for the development of nuclear technology in China. With the trends to globalization of economic development, civilian applications of nuclear technology will have to be involved in international co-operation and competitive world markets to narrow the gap between China and other developed countries in the world in the next century. (author)

IAEA activities in technology development for advanced water-cooled nuclear power plants

International Nuclear Information System (INIS)

Juhn, Poong Eil; Kupitz, Juergen; Cleveland, John; Lyon, Robert; Park, Je Won

2003-01-01

As part of its Nuclear Power Programme, the IAEA conducts activities that support international information exchange, co-operative research and technology assessments and advancements with the goal of improving the reliability, safety and economics of advanced water-cooled nuclear power plants. These activities are conducted based on the advice, and with the support, of the IAEA Department of Nuclear Energy's Technical Working Groups on Advanced Technologies for Light Water Reactors (LWRs) and Heavy Water Reactors (HWRs). Assessments of projected electricity generation costs for new nuclear plants have shown that design organizations are challenged to develop advanced designs with lower capital costs and short construction times, and sizes, including not only large evolutionary plants but also small and medium size plants, appropriate to grid capacity and owner financial investment capability. To achieve competitive costs, both proven means and new approaches should be implemented. The IAEA conducts activities in technology development that support achievement of improved economics of water-cooled nuclear power plants (NPPs). These include fostering information sharing and cooperative research in thermo-hydraulics code validation; examination of natural circulation phenomena, modelling and the reliability of passive systems that utilize natural circulation; establishment of a thermo-physical properties data base; improved inspection and diagnostic techniques for pressure tubes of HWRs; and collection and balanced reporting from recent construction and commissioning experiences with evolutionary water-cooled NPPs. The IAEA also periodically publishes Status Reports on global development of advanced designs. (author)

Engineering and technology in the deconstruction of nuclear materials production facilities

International Nuclear Information System (INIS)

Kingsley, R.S.; Reynolds, W.E.; Heffner, D.C.

1996-01-01

Technology and equipment exist to support nuclear facility deactivation, decontamination, and decommissioning. In reality, this statement is not surprising because the nuclear industry has been decontaminating and decommissioning production plants for decades as new generations of production technology were introduced. Since the 1950s, the Babcock and Wilcox Company (B ampersand W) has operated a number of nuclear materials processing facilities to manufacture nuclear fuel for the commercial power industry and the U.S. Navy. These manufacturing facilities included a mixed oxide (PuO 2 -UO 2 ) nuclear fuel manufacturing plant, low- and high-enriched uranium (HEU/LEU) chemical and fuel plants, and fuel assembly plants. In addition, B ampersand W designed and build a major nuclear research center in Lynchburg, Virginia, to support these nuclear fuel manufacturing activities and to conduct nuclear power research. These nuclear research facilities included two research reactors, a hot-cell complex for nuclear materials research, four critical experiment facilities, and a plutonium fuels research and development facility. This article describes the B ampersand W deactivation, decomtanimation, and decommisioning program

Strategy for Nuclear Technology Education at Uppsala University

International Nuclear Information System (INIS)

Osterlund, M.; Hakansson, A.; Tengborn, E.

2010-01-01

After the TMI accident 1979, and later the Tjernobyl accident, the future of nuclear power was vividly debated in Sweden. The negative public opinion governed a number of political decisions that marked an ambition to out-phase nuclear power prior to 2010. Due to this, the student's interest in nuclear technology ceased and together with the fact that public funding to nuclear technology was withdrawn, academic research and education within the field were effectively dismounted. In the beginning of 1990 it became clear to the society that nuclear power could not easily be closed down and the issue of the future competence supply to the nuclear industry was initiated. In the mid-nineties the situation became acute due to the fact that personnel in the nuclear industry started to retire in an increasing pace necessitating measures to be taken in order to secure the future operation of the nuclear power plants. In the year 2000, the Swedish nuclear power plants, Westinghouse Electric Sweden and the Swedish Radiation Safety Authority embarked a project together with the three major universities in the field, Uppsala University, The Royal Institute of Technology and Chalmers University of Technology. The aim of this project was to define a financial platform for reconstructing the Swedish research and education in nuclear technology. The project, named the Swedish Centre for Nuclear Technology (SKC), has during a decade been the major financier to nuclear technology research and education. Using funding from SKC, Uppsala University formulated a strategy along two tracks: 1) Instead of creating ambitious master programs in nuclear technology, the already existing engineering programs in a wide range of fields were utilized to expose as many students as possible to nuclear technology. 2) A program was initiated together with the nuclear industry aiming at educating newly employed personnel. The result is encouraging; starting from essentially zero, typically 100

Annual meeting on nuclear technology 2005. Proceedings

International Nuclear Information System (INIS)

2005-03-01

The proceedings of the annual meeting on nuclear technology 2005 covers the following issues: (1) reactor physics and methods of calculation: design and transients; method development and validation; (2): thermodynamics and fluid dynamics: analytical thermohydraulics for existing reactors; experiments and operational behavior; analytical methods for innovative reactors; (3) Safety of nuclear installations - methods, analysis, results: special problems; PSA and in-vessel phenomena; ex-vessel phenomena; (4) front end and back end of the fuel cycle, radioactive waste, storage: intermediate storage of fuel elements, waste treatment, (5) fuel elements and core components: fuel elements, new methods in the interpretation, manufacturing and service; (6) operation of nuclear installations: experience with the operation of NPPs; management systems, digital instrumentation and control of NPPs revision management; (7) decommissioning of nuclear installations: concepts and strategies for decommissioning and dismantling; experiences with decommissioning projects; (8) fusion technology: fusion facilities; materials and test facility; cryo technique and simulations; (9) research reactors: building new and backfitting of existing research reactors; current development; dismantling of research reactors; (10) advanced reactor concepts, energy systems, energy economics; (11) communication with the public; (12) component materials, fabrication and service behavior: degradation effects of component materials; component behavior; (13): radiation protection: PSA and in-vessel phenomena, ex-vessel phenomena.

Contributions to nuclear safety and radiation technologies in Ukraine by the Science and Technology Center in Ukraine (STCU)

Energy Technology Data Exchange (ETDEWEB)

Taranenko, L. E-mail: lyubov@stcu.kiev.ua; Janouch, F.; Owsiacki, L

2001-06-01

This paper presents Science and Technology Center in Ukraine (STCU) activities devoted to furthering nuclear and radiation safety, which is a prioritized STCU area. The STCU, an intergovernmental organization with the principle objective of non-proliferation, administers financial support from the USA, Canada, and the EU to Ukrainian projects in various scientific and technological areas; coordinates projects; and promotes the integration of Ukrainian scientists into the international scientific community, including involving western collaborators. The paper focuses on STCU's largest project to date 'Program Supporting Y2K Readiness at Ukrainian NPPs' initiated in April 1999 and designed to address possible Y2K readiness problems at 14 Ukrainian nuclear reactors. Other presented projects demonstrate a wide diversity of supported directions in the fields of nuclear and radiation safety, including reactor material improvement ('Improved Zirconium-Based Elements for Nuclear Reactors'), information technologies for nuclear industries ('Ukrainian Nuclear Data Bank in Slavutich'), and radiation health science ('Diagnostics and Treatment of Radiation-Induced Injuries of Human Biopolymers')

Nuclear technology in Peru

International Nuclear Information System (INIS)

Montoya, M.

1993-01-01

This book deals with the Nuclear Energy in Peru. It consists of ten chapters. In the first chapter is presented a rapid overview on nuclear science history. The second chapter describes the nuclear proliferation and the nuclear competition in South America. The nuclear organization in Peru, the Peruvian Institute of Nuclear Energy, and the main centers are described in the third chapter. The following chapters deals with peruvian advances in nuclear medicine, agriculture and food, nuclear application to industry, hydrology, earth sciences and environmental considerations. In the last chapter, the perspectives for nuclear science and technology in Peru are described from the inter institutional cooperation point of view. This book also includes appendix and bibliography. (author)

Design concepts for a nuclear digital instrumentation and control system platform

International Nuclear Information System (INIS)

Ou, T. C.; Chen, C. K.; Chen, P. J.; Shyu, S. S.; Lee, C. L.; Hsieh, S. F.

2010-10-01

The objective of this paper is to present the development results of the nuclear instrumentation and control system in Taiwan. As the Taiwan nuclear power plants age, the need to consider upgrading of both their safety and non-safety-related instrumentation and control systems becomes more urgent. Meanwhile, the digital instrumentation and control system that is based on current fast evolving electronic and information technologies are difficult to maintain effectively. Therefore, Institute of Nuclear Energy Research was made a decision to promote the Taiwan Nuclear Instrumentation and Control System project to collaborate with domestic electronic industry to establish self-reliant capabilities on the design, manufacturing, and application of nuclear instrumentation and control systems with newer technology. In the case of safety-related applications like nuclear instrumentation and control, safety-oriented quality control is required. In order to establish a generic qualified digital platform, the world-wide licensing experience should be considered in the licensing process. This paper describes the qualification and certification tools by IEC 61508 for design and development of safety related equipment and explains the basis for many decisions made while performing the digital upgrade. (Author)

AP1000, a nuclear central of advanced design

International Nuclear Information System (INIS)

Hernandez M, N.; Viais J, J.

2005-01-01

The AP1000 is a design of a nuclear reactor of pressurized water (PWR) of 1000 M We with characteristic of safety in a passive way; besides presenting simplifications in the systems of the plant, the construction, the maintenance and the safety, the AP1000 is a design that uses technology endorsed by those but of 30 years of operational experience of the PWR reactors. The program AP1000 of Westinghouse is focused to the implementation of the plant to provide improvements in the economy of the same one and it is a design that is derived directly of the AP600 designs. On September 13, 2004 the US-NRC (for their initials in United States- Nuclear Regulatory Commission) approved the final design of the AP1000, now Westinghouse and the US-NRC are working on the whole in a complete program for the certification. (Author)

Intelligent Digitized Design Systems for the Management of Design Knowledge Related to Nuclear R&D Institutes

International Nuclear Information System (INIS)

Zheng, M.; Minglu, W.

2016-01-01

Full text: Nuclear R&D is highly knowledge-intensive. With the rapid advent and development of modern information technology, knowledge management in nuclear industry has been provided with new approaches and possibilities. This article introduces a framework of intelligent digitized design system in nuclear R&D phase and finds answer to knowledge application, internal process optimization, experience feedback and further innovation. This framework utilizing digitalization and informatization finds a way to incorporate the process of the “Socialization, Externalization, Combination, Internalization” (SECI) model which include intelligent design process, integrated design software, smart verification and validation simulation platform, experiment data management platform, online monitoring platform and digital twin nuclear power plant, etc. The following case study gives a clear picture of what and how knowledge management has been performed under this framework. Furthermore, important lessons have been summarized. (author

Inherently safe technologies-chemical and nuclear

International Nuclear Information System (INIS)

Weinberg, A.M.

1984-01-01

Probabilistic risk assessments show an inverse relationship between the likelihood and the consequences of nuclear and chemical plant accidents, but the Bhopal accident has change public complacency about the safety of chemical plants to such an extent that public confidence is now at the same low level as with nuclear plants. The nuclear industry's response was to strengthen its institutions and improve its technologies, but the public may not be convinced. One solution is to develop reactors which do not depend upon the active intervention of humans of electromechanical devices to deal with emergencies, but which have physical properties that limit the possible temperature and power of a reactor. The Process Inherent Ultimately Safe and the modular High-Temperature Gas-Cooled reactors are two possibilities. the chemical industry needs to develop its own inherently safe design precepts that incorporate smallness, safe processes, and hardening against sabotage. 5 references

Safeguards by Design - Experiences from New Nuclear Installation

International Nuclear Information System (INIS)

Okko, O.; Honkamaa, T.; Kuusi, A.; Rautjaervi, J.

2010-01-01

energy, the world-wide nuclear technology holders, facility designers, manufacturers and supply organisations should be invited to participate in the development, construction and operation of safe, secure and efficiently safeguarded nuclear installations. (author)

Strengthened International Nuclear Safeguards; burdens and Effects on Nuclear Technology Development

International Nuclear Information System (INIS)

Badawy, I.

2000-01-01

The present paper deals with the recent direction of strengthening the international nuclear safeguards and the effects on the development of nuclear technology for peaceful applications. The new basic principles for strengthening the international nuclear control in the direction of undeclared nuclear activities are elaborated, and the national obligations are indicated. The burdens on the development of nuclear technology are discussed. Approaches are proposed in this work for coping with the present and future situations

Statistical evaluation of design-error related nuclear reactor accidents

International Nuclear Information System (INIS)

Ott, K.O.; Marchaterre, J.F.

1981-01-01

In this paper, general methodology for the statistical evaluation of design-error related accidents is proposed that can be applied to a variety of systems that evolves during the development of large-scale technologies. The evaluation aims at an estimate of the combined ''residual'' frequency of yet unknown types of accidents ''lurking'' in a certain technological system. A special categorization in incidents and accidents is introduced to define the events that should be jointly analyzed. The resulting formalism is applied to the development of U.S. nuclear power reactor technology, considering serious accidents (category 2 events) that involved, in the accident progression, a particular design inadequacy. 9 refs

Security technology discussion for emergency command system of nuclear power plant

International Nuclear Information System (INIS)

Liu Zhenjun

2014-01-01

Nuclear power plant emergency command system can provide valuable data for emergency personnel, such as the unit data, weather data, environmental radiation data. In the course of emergency response, the emergency command system provides decision support to quickly and effectively control and mitigate the consequences of the nuclear accident, to avoid and reduce the dose received by staff and the public, to protect the environment and the public. There are high performance requirements on the security of the system and the data transmission. Based on the previous project and new demand after the Fukushima incident, the security technology design of emergency system in nuclear power plant was discussed. The results show that the introduction of information security technology can effectively ensure the security of emergency systems, and enhance the capacity of nuclear power plant to deal with nuclear accidents. (author)

Technical guidelines for aseismic design of nuclear power plants

International Nuclear Information System (INIS)

Park, Y.J.; Hofmayer, C.H.

1994-06-01

This document is a translation, in its entirety, of the Japan Electric Association (JEA) publication entitled open-quotes Technical Guidelines for Aseismic Design of Nuclear Power Plants - JEAG 4601-1987.close quotes This guideline describes in detail the aseismic design techniques used in Japan for nuclear power plants. It contains chapters dealing with: (a)the selection of earthquake ground motions for a site, (b) the investigation of foundation and bedrock conditions, (c) the evaluation of ground stability and the effects of ground movement on buried piping and structures, (d) the analysis and design of structures, and (e) the analysis and design of equipment and distribution systems (piping, electrical raceways, instrumentation, tubing and HVAC duct). The guideline also includes appendices which summarize data, information and references related to aseismic design technology

Proposal for a technology-neutral safety approach for new reactor designs

International Nuclear Information System (INIS)

2007-09-01

Many states are considering an expansion of their nuclear power generation programmes. Many of the technologies and concepts are new and innovative. The current design and licensing rules are applicable to mostly large water reactors and there are no accepted rules in place for design, safety assessment and licensing for new innovative nuclear power plants. This TECDOC proposes a (new) safety approach and a methodology to generate technology-neutral (i.e. independent of reactor technology) safety requirements and a 'safe design' for advanced and innovative reactors. The experience gained in decades of design and licensing, combined with the development of risk-based concepts, has provided insights that will form the basis for new safety rules and requirements. Many lessons learned acknowledge the importance of such concepts as safety goals and defence in depth and the benefits of integrating risk insights early in an iterative design process. A new safety approach will incorporate many of the new developments in these concepts. For example, the probabilistic elements of defence in depth will help define the cumulative provisions to compensate for uncertainty and incompleteness of our knowledge of accident initiation and progression. This TECDOC also identifies areas of work, which will require further definition, research and development and guidance on application. This publication is to be used as a guide to developing a new technology-neutral safety approach, and as a guide in the application of methodologies to define the safety requirements for an innovative reactor designs. The method proposes an integration of deterministic and probabilistic considerations with established principles and concepts such as safety goals and defence in depth. The TECDOC recommends that the structure of the new technology-neutral main pillars for the design and licensing of innovative nuclear reactors be developed following a top-down approach to reflect a newer risk-informed and

An Effective Method For Nuclear Technology Transfer

International Nuclear Information System (INIS)

Jeon, Jan Pung

1987-01-01

Three basic entities involved in the implementation of nuclear projects are the Owner, Regulatory Authority and Nuclear Industry. Their ultimate objective is to secure the safe, reliable and economical nuclear energy. For s successful nuclear power program, the owner should maintain a good relationship with the other entities and pursue an optimization of the objectives. On the other hand, he should manage projects along the well - planned paths in order to effectively learn the nuclear technology. One of the problems in the nuclear projects of developing countries was the absence of long - term technology development program, a limited local participation and the technical incapability. For the effective technology transfer, a motivation of the technology supplier and a readiness of the recipient to accommodate such technologies are required. Advanced technology is usually developed at considerable expense with the expectation that the developer will use it in furthering his own business. Therefore, he tends to be reluctant to transfer it to the others, particularly, to the potential competitors. There is a disinclination against further technology transfer beyond the minimum contractual obligation or the requirements by Government Regulatory. So, an additional commercial incentive must be provided to the developer

Automatic start-up system of nuclear reactor based on sequence control technology

International Nuclear Information System (INIS)

Zhang Yao; Zhang Dafa; Peng Huaqing

2009-01-01

A conceptive design of an automatic start-up system based on the sequence control for the nuclear reactors is given in this paper, so as to solve the problems during the start-up process, such as the long operation time, low automatic control level and high accident rate. The start-up process and its requirements are analyzed in detail at first. Then,the principle, the architecture, the key technologies of the automatic start-up system of nuclear reactors are designed and discussed. With the designed system, the automatic start-up of the nuclear reactor can be realized,the work load of the operator can be reduced,and the safety and efficiency of the nuclear power plant during its start-up can be improved. (authors)

Evaluation of a Business Case for Safeguards by Design in Nuclear Power Reactors

Energy Technology Data Exchange (ETDEWEB)

Wood, Thomas W.; Seward, Amy M.; Lewis, Valerie A.; Gitau, Ernest TN; Zentner, Michael D.

2012-12-01

Safeguards by Design (SbD) is a well-known paradigm for consideration and incorporation of safeguards approaches and associated design features early in the nuclear facility development process. This paradigm has been developed as part of the Next Generation Safeguards Initiative (NGSI), and has been accepted as beneficial in many discussions and papers on NGSI or specific technologies under development within NGSI. The Office of Nuclear Safeguards and Security funded the Pacific Northwest National Laboratory to examine the business case justification of SbD for nuclear power reactors. Ultimately, the implementation of SbD will rely on the designers of nuclear facilities. Therefore, it is important to assess the incentives which will lead designers to adopt SbD as a standard practice for nuclear facility design. This report details the extent to which designers will have compelling economic incentives to adopt SbD.

Progress in space nuclear reactor power systems technology development - The SP-100 program

Science.gov (United States)

Davis, H. S.

1984-01-01

Activities related to the development of high-temperature compact nuclear reactors for space applications had reached a comparatively high level in the U.S. during the mid-1950s and 1960s, although only one U.S. nuclear reactor-powered spacecraft was actually launched. After 1973, very little effort was devoted to space nuclear reactor and propulsion systems. In February 1983, significant activities toward the development of the technology for space nuclear reactor power systems were resumed with the SP-100 Program. Specific SP-100 Program objectives are partly related to the determination of the potential performance limits for space nuclear power systems in 100-kWe and 1- to 100-MW electrical classes. Attention is given to potential missions and applications, regimes of possible space power applicability, safety considerations, conceptual system designs, the establishment of technical feasibility, nuclear technology, materials technology, and prospects for the future.

To revisit economics of nuclear technology. Lessons from the learning of a complex technology by major accidents

International Nuclear Information System (INIS)

Finon, Dominique

2012-05-01

The Fukushima accident raises again the issue of the social and economic viability of nuclear technology. To re-evaluate this viability, we analyse the past process of internalisation of external costs of nuclear energy, which present the specificities to be chanted by accidents and has had a constant effect of complexification. This process has provoked a de-organisation of the classical learning process reflected in constant cost increases and the change of social preferences, to end up by the lack of competitiveness before climate policies. Independent institutions of safety regulation have become essential elements of the social embeddedness of nuclear technology at the expense of technology stability and standardization, condition of its competitiveness. In this perspective, the paper argues that the new sequence of social costs' internalization opened by Fukushima will have limited effects on costs, because of anterior steps of safety improvements. Nuclear technology complexification reaches its asymptote: it is being to overcome the challenge of 'learning by major accidents'. On the other hand nuclear institutions must be re-designed in such a way that it could guarantee maximum safety records and minimum residual risks by going to the other root of the safety issue, the degree of independence and capabilities of the safety authorities in every country, what cannot be decreed. It is nevertheless at this price that could be preserved the global public good of the social acceptance of nuclear technology by limiting drastically chance of new accidents. (author)

Y-Notes; Introductory Sessions on Nuclear Technology

International Nuclear Information System (INIS)

2001-01-01

This chapter is divided into next parts: What is 'Y-Notes ; Young generation opening session; Nuclear education and transfer of know-how; Nuclear technology; Other applications of nuclear technology; Nuclear programs and technical cooperation; Political aspects; Environment and safety; Communication and public perception; Economics; Fuel cycle challenges; Video

Let nuclear technology create new brilliancy for china's sustainable development

International Nuclear Information System (INIS)

Du Xiangwan

2008-01-01

This paper summarizes the development and application directions of nuclear technology, including five aspects: nuclear technology and energy nuclear technology and medicine, nuclear anclear analysis technology, nuclear radiation technology, astronautics and voyage's nuclear power, etc. The paper discusses the importance of them to sustainable development and generalizes the development trilogy of nuclear science and technology and its prospect. (authors)

Environmental assessment report: Nuclear Test Technology Complex

International Nuclear Information System (INIS)

Tonnessen, K.; Tewes, H.A.

1982-08-01

The US Department of Energy (USDOE) is planning to construct and operate a structure, designated the Nuclear Test Technology Complex (NTTC), on a site located west of and adjacent to the Lawrence Livermore National Laboratory. The NTTC is designed to house 350 nuclear test program personnel, and will accommodate the needs of the entire staff of the continuing Nuclear Test Program (NTP). The project has three phases: land acquisition, facility construction and facility operation. The purpose of this environmental assessment report is to describe the activities associated with the three phases of the NTTC project and to evaluate potential environmental disruptions. The project site is located in a rural area of southeastern Alameda County, California, where the primary land use is agriculture; however, the County has zoned the area for industrial development. The environmental impacts of the project include surface disturbance, high noise levels, possible increases in site erosion, and decreased air quality. These impacts will occur primarily during the construction phase of the NTTC project and can be mitigated in part by measures proposed in this report

Seismic design considerations of nuclear fuel cycle facilities

International Nuclear Information System (INIS)

2001-10-01

An Advisory Group Meeting (AGM) on Seismic Technologies of Nuclear Fuel Cycle Facilities was convened in Vienna from 12 to 14 November 1997. The main objective of the meeting was the investigation of the present status of seismic technologies in nuclear fuel cycle facilities in Member States as a starting point for understanding of the most important directions and trends of national initiatives, including research and development, in the area of seismic safety. The AGM gave priority to the establishment of a consistent programme for seismic assessment of nuclear fuel cycle facilities worldwide. A consultants meeting subsequently met in Vienna from 16 to 19 March 1999. At this meeting the necessity of a dedicated programme was further supported and a technical background to the initiative was provided. This publication provides recommendations both for the seismic design of new plants and for re-evaluation projects of nuclear fuel cycle facilities. After a short introduction of the general IAEA approach, some key contributions from Member State participants are presented. Each of them was indexed separately

Nuclear technology databases and information network systems

International Nuclear Information System (INIS)

Iwata, Shuichi; Kikuchi, Yasuyuki; Minakuchi, Satoshi

1993-01-01

This paper describes the databases related to nuclear (science) technology, and information network. Following contents are collected in this paper: the database developed by JAERI, ENERGY NET, ATOM NET, NUCLEN nuclear information database, INIS, NUclear Code Information Service (NUCLIS), Social Application of Nuclear Technology Accumulation project (SANTA), Nuclear Information Database/Communication System (NICS), reactor materials database, radiation effects database, NucNet European nuclear information database, reactor dismantling database. (J.P.N.)

Interviews concerning topical questions in nuclear technology

International Nuclear Information System (INIS)

Segatz, U.; Schatz, A.; Stephany, M.; Michaelis, H.

1978-01-01

On the occasion of the Nuclex meeting, October 3-7, 1978, Basle/Switzerland, the editorial department of 'Atom und Strom' questioned some leading scientists in nuclear technology on particularly relevant topics. The following subjects were discussed: - How long can we do without nuclear energy, - Modern technology for nuclear power plants, - Nuclear fuel cycle and environment, - Nuclear energy and European Communities, - Nuclear energy and its risks (reflections on incidents). (orig./UA) [de

A Study on the Linkage between Nano Fusion Technology and Nuclear Technology

International Nuclear Information System (INIS)

Jeong, Ik; Lim, Chae Young; Lee, Jong Hee

2009-02-01

1) A survey of national energy policy trends in major nation - to secure renewal energy in the level of making a plan to supply national energy in the future - Tendency of energy policy based on Europe 2) A survey of the nano technology development - Status of major nano technology development - Developmental direction of nano technology related to nuclear energy 3) the nano technology development related with nuclear - high-temperature nuclear reactor by applying nano science and technology under quick development - materials required to high-level radioactive wastes treatment facility - develop materials of nuclear fusion facility in the long-term view 4) Innovation system of nano technology - Energy source -> conversion to energy -> distribution of energy -> energy storage -> energy use

Nuclear imaging technology and global requirements

International Nuclear Information System (INIS)

Lele, R.D.

1991-01-01

After a brief review of the present state of availability of nuclear medicine services in the countries of world, a mention has been made of WHO programme on nuclear medicine. Nuclear medicine services in the developing countries are dependent on the availability of appropriate instrumentation and radiopharmaceuticals at affordable costs and existence of basic infrastructure required for giving such services. Basic infrastructure requirements are stable power supplies, air-conditioning systems, preventive maintenance and repair facilities. These are discussed. It is pointed out that the use of rectilinear scanners with 113m In instead of costly gamma cameras is still relevant in the third world countries. Need to develop a too low-cost gamma camera is emphasized. Electronics Corporation of India Ltd has plans to manufacture such cameras. Design of this camera is described. Foreign collaboration or technology transfer through concerned governement department needs to be explored so that the benefits of nuclear medicine can be brought to the third world countries by 2000 AD. (M.G.B.). 2 tabs

History of nuclear technology development in Japan

Energy Technology Data Exchange (ETDEWEB)

Yamashita, Kiyonobu, E-mail: yamashita.kiyonobu@jaea.go.jp [Visiting Professor, at the Faculty of Petroleum and Renewable Energy Engineering, University Teknologi Malaysia Johor Bahru 81310 (Malaysia); General Advisor Nuclear HRD Centre, Japan Atomic Energy Agency, TOKAI-mura, NAKA-gun, IBARAKI-ken, 319-1195 (Japan)

2015-04-29

Nuclear technology development in Japan has been carried out based on the Atomic Energy Basic Act brought into effect in 1955. The nuclear technology development is limited to peaceful purposes and made in a principle to assure their safety. Now, the technologies for research reactors radiation application and nuclear power plants are delivered to developing countries. First of all, safety measures of nuclear power plants (NPPs) will be enhanced based on lesson learned from TEPCO Fukushima Daiichi NPS accident.

History of nuclear technology development in Japan

Science.gov (United States)

Yamashita, Kiyonobu

2015-04-01

Nuclear technology development in Japan has been carried out based on the Atomic Energy Basic Act brought into effect in 1955. The nuclear technology development is limited to peaceful purposes and made in a principle to assure their safety. Now, the technologies for research reactors radiation application and nuclear power plants are delivered to developing countries. First of all, safety measures of nuclear power plants (NPPs) will be enhanced based on lesson learned from TEPCO Fukushima Daiichi NPS accident.

History of nuclear technology development in Japan

International Nuclear Information System (INIS)

Yamashita, Kiyonobu

2015-01-01

Nuclear technology development in Japan has been carried out based on the Atomic Energy Basic Act brought into effect in 1955. The nuclear technology development is limited to peaceful purposes and made in a principle to assure their safety. Now, the technologies for research reactors radiation application and nuclear power plants are delivered to developing countries. First of all, safety measures of nuclear power plants (NPPs) will be enhanced based on lesson learned from TEPCO Fukushima Daiichi NPS accident

Economy and technology roles played by nuclear power

International Nuclear Information System (INIS)

Yamada, Eiji

1985-01-01

On the basis of the survey analysis made by Atomic Energy Commission on the roles in economy and technology played in the nuclear energy development and utilization, the following are described: economic roles in nuclear energy development and utilization (the present state of nuclear power industry in Japan and the economy effects); technological roles in the same (the present state of nuclear power technology in Japan and the technology effects). The economy effects in other areas are on higher level than in other industries etc. Then, in the technology effects, system technology and quality control in the nuclear power possess significant effects in other areas. While the nuclear energy development and utilization is important in Japan's energy security, it is contributing largely to the economy and society in Japan. (Mori, K.)

Nuclear fuel cycle: research and development and push technologies

International Nuclear Information System (INIS)

Oliveira, Wagner dos Santos

2002-01-01

The scope of this work is to show the importance of 'push technologies in the development of the Nuclear Fuel Cycle more specifically the so called 'Projeto Conversao' PROCON. This R and D activities lead to the design of special equipment, new metallic and polymer materials. (author)

Advanced nuclear reactor types and technologies

International Nuclear Information System (INIS)

Ignatiev, V.; Devell, L.

1995-01-01

The document is a comprehensive world-wide catalogue of concepts and designs of advanced fission reactor types and fuel cycle technologies. Two parts have been prepared: Part 1 Reactors for Power Production and Part 2 Heating and Other Reactor Applications. Part 3, which will cover advanced waste management technology, reprocessing and disposal for different nuclear fission options is planned for compilation during 1995. The catalogue was prepared according to a special format which briefly presents the project title, technical approach, development status, application of the technology, reactor type, power output, and organization which developed these designs. Part 1 and 2 cover water cooled reactors, liquid metal fast reactors, gas-cooled reactors and molten salt reactors. Subcritical accelerator-driven systems are also considered. Various reactor applications as power production, heat generation, ship propulsion, space power sources and transmutation of such waste are included. Each project is described within a few pages with the main features of an actual design using a table with main technical data and figure as well as references for additional information. Each chapter starts with an introduction which briefly describes main trends and approaches in this field. Explanations of terms and abbreviations are provided in a glossary

Advanced nuclear reactor types and technologies

Energy Technology Data Exchange (ETDEWEB)

Ignatiev, V [ed.; Feinberg, O; Morozov, A [Russian Research Centre ` Kurchatov Institute` , Moscow (Russian Federation); Devell, L [Studsvik Eco and Safety AB, Nykoeping (Sweden)

1995-07-01

The document is a comprehensive world-wide catalogue of concepts and designs of advanced fission reactor types and fuel cycle technologies. Two parts have been prepared: Part 1 Reactors for Power Production and Part 2 Heating and Other Reactor Applications. Part 3, which will cover advanced waste management technology, reprocessing and disposal for different nuclear fission options is planned for compilation during 1995. The catalogue was prepared according to a special format which briefly presents the project title, technical approach, development status, application of the technology, reactor type, power output, and organization which developed these designs. Part 1 and 2 cover water cooled reactors, liquid metal fast reactors, gas-cooled reactors and molten salt reactors. Subcritical accelerator-driven systems are also considered. Various reactor applications as power production, heat generation, ship propulsion, space power sources and transmutation of such waste are included. Each project is described within a few pages with the main features of an actual design using a table with main technical data and figure as well as references for additional information. Each chapter starts with an introduction which briefly describes main trends and approaches in this field. Explanations of terms and abbreviations are provided in a glossary.

Panel session on the state of the art in nuclear reactor technology

International Nuclear Information System (INIS)

Roche, R.

1977-01-01

The state of the art in the technology of pressure vessels and piping of the primary cooling circuit of nuclear steam supply systems is discussed. Design and analysis are considered in the frame of the two types of nuclear reactor retained in France (PWR and the pool type LMFBR). Designing nuclear pressure vessels asks for some more specific Codes and Standards than for conventional vessels, and the stress analysis complementing by a direct comparison between operating loads and failure loads is a mandatory practice in France. As for pool type LMFBR, the structural problems of the nuclear vessel are essentially due to component shape, small thickness, and large stress range

Nuclear Malaysia Strategic Approach Towards Public Acceptance on Nuclear Technology

International Nuclear Information System (INIS)

Hasfazilah Hassan; Redzuan Mohamad; Abdul Halim Jumat; Sabariah Kader Ibrahim

2016-01-01

Full text: This paper describes the strategic approach taken by Malaysian Nuclear Agency in carrying out public information and public acceptance on nuclear technology activities. The main objective of this study is to ensure that public and stake holders are continuously getting correct information from credible sources. Through the feedback received, comprehensive and holistic approach provides the desired impact. Obtaining the correct information from credible sources culture should always be inculcate to ensure that the benefits of nuclear technologies can be practiced and accepted by civil society without prejudice. Through strategic approach and activities implemented, monitoring and review, and measurement of the effectiveness of ongoing programs are expected to increase public awareness of the importance and contribution of nuclear technology in Malaysia. (author)

Nuclear Science and Technology for Thai Society

International Nuclear Information System (INIS)

Thailand Institute of Nuclear Technology, Bangkok

2009-07-01

Full text: Full text: The 11th conference on the nuclear science and technology was held on 2-3 July 2009 in Bangkok. This conference contain paper on non-power applications of nuclear technology in medicine, agriculture and industry. These application include irradiation of food for the infestation tram technologies used in diagnosis and therapy and radiation chemistry important to industrial processes. Some technologies which evolved from the development of nuclear power industry are also discussed

Nuclear renaissance, public perception and design criteria: An exploratory review

International Nuclear Information System (INIS)

Goodfellow, Martin J.; Williams, Hugo R.; Azapagic, Adisa

2011-01-01

There is currently an international drive to build new nuclear power plants, bringing about what is being termed a 'nuclear renaissance'. However, the public perception of nuclear energy has historically been, and continues to be, a key issue, particularly in light of the Fukushima nuclear incident. This paper discusses the disparity between perceived and calculated risks based on the last four decades of research into risk perception. The leading psychological and sociological theories, Psychometric Paradigm and Cultural Theory, respectively, are critically reviewed. The authors then argue that a new nuclear-build policy that promotes a broader approach to design incorporating a wider range of stakeholder inputs, including that of the lay public, may provide a means for reducing the perceived risk of a nuclear plant. Further research towards such a new approach to design is proposed, based on integrating expert and lay stakeholder inputs and taking into account broader socio-cultural factors whilst maintaining the necessary emphasis on safety, technological development, economics and environmental sustainability. - Highlights: → Globally, a number of countries are investing in or considering building new nuclear plants. → Public acceptance of nuclear safety is important to continuing new nuclear build efforts. → Theories are discussed attempting to explain the public perception of nuclear safety. → A socially informed design process is proposed which could assist in ensuring public support. → Further research to understand how this design process might be performed is proposed.

Design requirements for new nuclear reactor facilities in Canada

International Nuclear Information System (INIS)

Shim, S.; Ohn, M.; Harwood, C.

2012-01-01

The Canadian Nuclear Safety Commission (CNSC) has been establishing the regulatory framework for the efficient and effective licensing of new nuclear reactor facilities. This regulatory framework includes the documentation of the requirements for the design and safety analysis of new nuclear reactor facilities, regardless of size. For this purpose, the CNSC has published the design and safety analysis requirements in the following two sets of regulatory documents: 1. RD-337, Design of New Nuclear Power Plants and RD-310, Safety Analysis for Nuclear Power Plants; and 2. RD-367, Design of Small Reactor Facilities and RD-308, Deterministic Safety Analysis for Small Reactor Facilities. These regulatory documents have been modernized to document past practices and experience and to be consistent with national and international standards. These regulatory documents provide the requirements for the design and safety analysis at a high level presented in a hierarchical structure. These documents were developed in a technology neutral approach so that they can be applicable for a wide variety of water cooled reactor facilities. This paper highlights two particular aspects of these regulatory documents: The use of a graded approach to make the documents applicable for a wide variety of nuclear reactor facilities including nuclear power plants (NPPs) and small reactor facilities; and, Design requirements that are new and different from past Canadian practices. Finally, this paper presents some of the proposed changes in RD-337 to implement specific details of the recommendations of the CNSC Fukushima Task Force Report. Major changes were not needed as the 2008 version of RD-337 already contained requirements to address most of the lessons learned from the Fukushima event of March 2011. (author)

Scenario-based roadmapping assessing nuclear technology development paths for future nuclear energy system scenarios

International Nuclear Information System (INIS)

Van Den Durpel, Luc; Roelofs, Ferry; Yacout, Abdellatif

2009-01-01

Nuclear energy may play a significant role in a future sustainable energy mix. The transition from today's nuclear energy system towards a future more sustainable nuclear energy system will be dictated by technology availability, energy market competitiveness and capability to achieve sustainability through the nuclear fuel cycle. Various scenarios have been investigated worldwide each with a diverse set of assumptions on the timing and characteristics of new nuclear energy systems. Scenario-based roadmapping combines the dynamic scenario-analysis of nuclear energy systems' futures with the technology roadmap information published and analysed in various technology assessment reports though integrated within the nuclear technology roadmap Nuclear-Roadmap.net. The advantages of this combination is to allow mutual improvement of scenario analysis and nuclear technology roadmapping providing a higher degree of confidence in the assessment of nuclear energy system futures. This paper provides a description of scenario-based roadmapping based on DANESS and Nuclear-Roadmap.net. (author)

Evaluation of mini super computers for nuclear design applications

International Nuclear Information System (INIS)

Altomare, S.; Baradari, F.

1987-01-01

The evolution of the mini super computers will force changes from the current environment of performing nuclear design calculations on mainframe computers (such as a CRAY) to mini super computers. This change will come about for a number of reasons. First, the mini super computers currently available in the marketplace offer the power and speed comparable to mainframes and can provide the capability to support highly computer intensive calculations. Second, the equipment is physically smaller and can easily be installed and operated without extensive investments in facilities and operations support. Third, the computer capacity can be acquired with as much needed memory, disk, and tape capacity as may be needed. Another reasons is that the performance/cost ratio has increased drastically as hardware costs have decreased. A study was conducted at the Westinghouse Commercial Nuclear Fuel Division (CNFD) to evaluate the mini super computers for use in nuclear core design. As a result of this evaluation, Westinghouse CNFD is offering a combined hardware/software technology transfer package for core design. This package provides the utility designer with a totally dedicated mini super computer comparable in speed to the CRAY 1S with sufficient capacity for a sizable design group to perform the engineering activities related to nuclear core design and operations support. This also assures the utility of being totally compatible with the CNFD design codes, thus assuring total update compatibility

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

International Nuclear Information System (INIS)

Metcalf, Richard; Bean, Robert

2009-01-01

The International Atomic Energy Agency (IAEA) implements nuclear safeguards and verifies countries are compliant with their international nuclear safeguards agreements. One of the key provisions in the safeguards agreement is the requirement that the country provide nuclear facility design and operating information to the IAEA relevant to safeguarding the facility, and at a very early stage. , This provides the opportunity for the IAEA to verify the safeguards-relevant features of the facility and to periodically ensure that those features have not changed. The national authorities (State System of Accounting for and Control of Nuclear Material - SSAC) provide the design information for all facilities within a country to the IAEA. The design information is conveyed using the IAEA's Design Information Questionnaire (DIQ) and specifies: (1) Identification of the facility's general character, purpose, capacity, and location; (2) Description of the facility's layout and nuclear material form, location, and flow; (3) Description of the features relating to nuclear material accounting, containment, and surveillance; and (4) Description of existing and proposed procedures for nuclear material accounting and control, with identification of nuclear material balance areas. The DIQ is updated as required by written addendum. IAEA safeguards inspectors examine and verify this information in design information examination (DIE) and design information verification (DIV) activities to confirm that the facility has been constructed or is being operated as declared by the facility operator and national authorities, and to develop a suitable safeguards approach. Under the Next Generation Safeguards Initiative (NGSI), the National Nuclear Security Administrations (NNSA) Office of Non-Proliferation and International Security identified the need for more effective and efficient verification of design information by the IAEA for improving international safeguards in the future

Recommended numerical nuclear physics data for cutting-edge nuclear technology applications

International Nuclear Information System (INIS)

Ganesan, S.; Srivenkatesan, R.; Anek Kumar; Murthy, C.S.R.C.; Dhekne, P.S.

2005-01-01

This paper introduces some aspects of online nuclear data services at Mumbai as part of today's technology of sharing knowledge of the recommended numerical nuclear physics data for nuclear applications. The physics foundation for cutting-edge technology applications is significantly strengthened by such knowledge generation and sharing techniques. A BARC server is presently mirroring the nuclear data services of the IAEA, Vienna. The users can get all the nuclear data information much faster from the BARC nuclear data mirror website that is now fully operational. The nuclear community is encouraged to develop the habit of accessing the website for recommended values of nuclear data for use in research and applications. The URL is: www-nds.indcentre.org.in (author)

Consideration on the interaction between society and nuclear technology

International Nuclear Information System (INIS)

Shinoda, Yoshihiko

2007-01-01

A social conflict over nuclear technology arises from the different interactions between society and nuclear technology. The purpose of this review is to grasp the essential points of this social conflict from a social viewpoint. These essential points can be discerned by interpreting results of polls about nuclear technology and the future of society in general. As a result, attitudes towards nuclear technology can be explained in terms of differences of general views on society such as social order or social progress. The attitudes of people toward nuclear technology were divided into strong agreement, weak agreement, weak objection and strong objection in order to obtain useful information for clarification of social conflict on this issue. Results of polls of people who have weak agreement for nuclear technology reveal their ambivalence about nuclear technology. This raises concern that further implementation of nuclear technology might cause these people to shift their views to objection. (author)

Nuclear integrated database and design advancement system

International Nuclear Information System (INIS)

Ha, Jae Joo; Jeong, Kwang Sub; Kim, Seung Hwan; Choi, Sun Young.

1997-01-01

The objective of NuIDEAS is to computerize design processes through an integrated database by eliminating the current work style of delivering hardcopy documents and drawings. The major research contents of NuIDEAS are the advancement of design processes by computerization, the establishment of design database and 3 dimensional visualization of design data. KSNP (Korea Standard Nuclear Power Plant) is the target of legacy database and 3 dimensional model, so that can be utilized in the next plant design. In the first year, the blueprint of NuIDEAS is proposed, and its prototype is developed by applying the rapidly revolutionizing computer technology. The major results of the first year research were to establish the architecture of the integrated database ensuring data consistency, and to build design database of reactor coolant system and heavy components. Also various softwares were developed to search, share and utilize the data through networks, and the detailed 3 dimensional CAD models of nuclear fuel and heavy components were constructed, and walk-through simulation using the models are developed. This report contains the major additions and modifications to the object oriented database and associated program, using methods and Javascript.. (author). 36 refs., 1 tab., 32 figs

Technology Roadmap Instrumentation, Control, and Human-Machine Interface to Support DOE Advanced Nuclear Energy Programs

Energy Technology Data Exchange (ETDEWEB)

Donald D Dudenhoeffer; Burce P Hallbert

2007-03-01

Instrumentation, Controls, and Human-Machine Interface (ICHMI) technologies are essential to ensuring delivery and effective operation of optimized advanced Generation IV (Gen IV) nuclear energy systems. In 1996, the Watts Bar I nuclear power plant in Tennessee was the last U.S. nuclear power plant to go on line. It was, in fact, built based on pre-1990 technology. Since this last U.S. nuclear power plant was designed, there have been major advances in the field of ICHMI systems. Computer technology employed in other industries has advanced dramatically, and computing systems are now replaced every few years as they become functionally obsolete. Functional obsolescence occurs when newer, more functional technology replaces or supersedes an existing technology, even though an existing technology may well be in working order.Although ICHMI architectures are comprised of much of the same technology, they have not been updated nearly as often in the nuclear power industry. For example, some newer Personal Digital Assistants (PDAs) or handheld computers may, in fact, have more functionality than the 1996 computer control system at the Watts Bar I plant. This illustrates the need to transition and upgrade current nuclear power plant ICHMI technologies.

AFRA Network for Education in Nuclear Science and Technology

International Nuclear Information System (INIS)

Hashim, N.; Wanjala, F.

2017-01-01

AFRA-NEST was Conceived at the AFRA Ministerial Conference held in Aswan in 2007. The main objective of AFRA-NEST is to facilitate operation and networking in higher education, training and related research in Nuclear Science (NS&T) in the African Region through: • Sharing of information and materials of nuclear education and training. The strategies for implementing the objectives are: the use ICT for web-based education and training,; recognition of Regional Designated Centres (RDCs) for professional nuclear education in nuclear science and technology, and organization of harmonized and accredited programs at tertiary levels for teaching and research in the various nuclear disciplines. The main function of the AFRA-NEST is to; foster sustainable human resource development and nuclear knowledge management; host the Cyber Learning Platform for Nuclear Education and Training for the AFRA region and to integrate all available higher education capabilities in Africa

Application of the V.R. technology to the 3D-CAD system for nuclear plant

International Nuclear Information System (INIS)

Katoh, Toshisada; Tanaka, Kazuo; Kasai, Yasusuke; Kimura, Katsumi; Nakakoshi, Tetsuhiro

1993-01-01

The technology of the V.R. (Virtual Reality) is expected to improve the interface between the human and the computer by reality and easiness. The application of the V.R. technology to the nuclear power plant will bring the wide-spread use of the computer in various fields such as plant planning, design, training, and operation. The combination of the 3D-CAD plant data and the V.R. technologies will be easy approach to realize these applications because the 3D-CAD data for nuclear plant is constructed in the design stage. The prototype system investigates the feasibility of V.R. technologies in the nuclear plant. The stereo-scopic device and the voice processing device has been integrated to 3D-CAD system by 1992. We confirmed that these devices have a good effect on the improvement of the interface between the man and the computer. (orig.)

Current Abstracts Nuclear Reactors and Technology

Energy Technology Data Exchange (ETDEWEB)

Bales, J.D.; Hicks, S.C. [eds.

1993-01-01

This publication Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database during the past month. Also included are US information obtained through acquisition programs or interagency agreements and international information obtained through acquisition programs or interagency agreements and international information obtained through the International Energy Agency`s Energy Technology Data Exchange or government-to-government agreements. The digests in NRT and other citations to information on nuclear reactors back to 1948 are available for online searching and retrieval on the Energy Science and Technology Database and Nuclear Science Abstracts (NSA) database. Current information, added daily to the Energy Science and Technology Database, is available to DOE and its contractors through the DOE Integrated Technical Information System. Customized profiles can be developed to provide current information to meet each user`s needs.

Nuclear Proliferation Technology Trends Analysis

Energy Technology Data Exchange (ETDEWEB)

Zentner, Michael D.; Coles, Garill A.; Talbert, Robert J.

2005-10-04

A process is underway to develop mature, integrated methodologies to address nonproliferation issues. A variety of methodologies (both qualitative and quantitative) are being considered. All have one thing in common, a need for a consistent set of proliferation related data that can be used as a basis for application. One approach to providing a basis for predicting and evaluating future proliferation events is to understand past proliferation events, that is, the different paths that have actually been taken to acquire or attempt to acquire special nuclear material. In order to provide this information, this report describing previous material acquisition activities (obtained from open source material) has been prepared. This report describes how, based on an evaluation of historical trends in nuclear technology development, conclusions can be reached concerning: (1) The length of time it takes to acquire a technology; (2) The length of time it takes for production of special nuclear material to begin; and (3) The type of approaches taken for acquiring the technology. In addition to examining time constants, the report is intended to provide information that could be used to support the use of the different non-proliferation analysis methodologies. Accordingly, each section includes: (1) Technology description; (2) Technology origin; (3) Basic theory; (4) Important components/materials; (5) Technology development; (6) Technological difficulties involved in use; (7) Changes/improvements in technology; (8) Countries that have used/attempted to use the technology; (9) Technology Information; (10) Acquisition approaches; (11) Time constants for technology development; and (12) Required Concurrent Technologies.

The Application of Nuclear Technology for a Better World

International Nuclear Information System (INIS)

Ita, E.B.

2015-01-01

Nuclear Technology is widely used in different areas and sector of our economy to better man kind and his environment. Peaceful applications of nuclear technology have several benefits to the world today. It is widely believed that nuclear technology is mainly used mainly for the production of electricity (Nuclear Power Plants – NPPs). Many are not aware of the other numerous benefits of nuclear technology. Nuclear technology can be applied in different fields for numerous benefits. Different sectors Nuclear Technology application can improve the living standard of man and his environment: – Food and Agriculture; – Medicine; – Industrial; – Energy; – Education; — Research and Development; – Environment. The benefits of the application of nuclear technology cannot be over emphasised. These benefits range from the improved quality of purified water we drink, the textiles we wear, improved quality of stored grains for preservation of foods, water analyses, improved transportation system work, drugs production, medical tests and analysis, clean environment through radioisotope techniques etc. The application of nuclear technology also gives a safer, greener, healthier and pollution free environment and atmosphere for human habitation. In my poster, the numerous benefits of the various applications of Nuclear Technology will be clearly enumerated and heighted. (author)

Development of Nuclear Fuel Remote Fabrication Technology

International Nuclear Information System (INIS)

Lee, Jung Won; Yang, M. S.; Kim, S. S. and others

2005-04-01

The aim of this study is to develop the essential technology of dry refabrication using spent fuel materials in a laboratory scale on the basis of proliferation resistance policy. The emphasis is placed on the assessment and the development of the essential technology of dry refabrication using spent fuel materials. In this study, the remote fuel fabrication technology to make a dry refabricated fuel with an enhanced quality was established. And the instrumented fuel pellets and mini-elements were manufactured for the irradiation testing in HANARO. The design and development technology of the remote fabrication equipment and the remote operating and maintenance technology of the equipment in hot cell were also achieved. These achievements will be used in and applied to the future back-end fuel cycle and GEN-IV fuel cycle and be a milestone for Korea to be an advanced nuclear country in the world

Application of smart transmitter technology in nuclear engineering measurements

International Nuclear Information System (INIS)

Kang, Hyun Gook; Seong, Poong Hyun

1993-01-01

By making use of the microprocessor technology, instrumentation system becomes intelligent. In this study a programmable smart transmitter is designed and applied to the nuclear engineering measurements. In order to apply the smart transmitter technology to nuclear engineering measurements, the digital time delay compensation function and water level change detection function are developed and applied in this work. The time compensation function compensates effectively the time delay of the measured signal, but it is found that the characteristics of the compensation function should be considered through its application. It is also found that the water level change detection function reduces the detection time to about 7 seconds by the signal processing which has the time constant of over 250 seconds and which has the heavy noise. (Author)

Evaluating Russian space nuclear reactor technology for United States applications

International Nuclear Information System (INIS)

Polansky, G.F.; Schmidt, G.L.; Voss, S.S.; Reynolds, E.L.

1994-01-01

Space nuclear power and nuclear electric propulsion are considered important technologies for planetary exploration, as well as selected earth orbit applications. The Nuclear Electric Propulsion Space Test Program (NEPSTP) was intended to provide an early flight demonstration of these technologies at relatively low cost through extensive use of existing Russian technology. The key element of Russian technology employed in the program was the Topaz II reactor. Refocusing of the activities of the Ballistic Missile Defense Organization (BMDO), combined with budgetary pressures, forced the cancellation of the NEPSTP at the end of the 1993 fiscal year. The NEPSTP was faced with many unique flight qualification issues. In general, the launch of a spacecraft employing a nuclear reactor power system complicates many spacecraft qualification activities. However, the NEPSTP activities were further complicated because the reactor power system was a Russian design. Therefore, this program considered not only the unique flight qualification issues associated with space nuclear power, but also with differences between Russian and United States flight qualification procedures. This paper presents an overview of the NEPSTP. The program goals, the proposed mission, the spacecraft, and the Topaz II space nuclear power system are described. The subject of flight qualification is examined and the inherent difficulties of qualifying a space reactor are described. The differences between United States and Russian flight qualification procedures are explored. A plan is then described that was developed to determine an appropriate flight qualification program for the Topaz II reactor to support a possible NEPSTP launch

Nuclear Measurement Technologies and Solutions Implemented during Nuclear Accident at Fukushima

International Nuclear Information System (INIS)

Morichi, M.; Toubon, H.; Bronson, Frazier; Venkataraman, Ram; Beaujoin, J.; Dubart, P.

2013-06-01

Fukushima accident imposed a stretch to nuclear measurement operational approach requiring in such emergency situation: fast concept development, fast system integration, deployment and start-up in a very short time frame. This paper is describing the Nuclear Measurement that AREVA-BUNM (CANBERRA) has realized and foresight at Fukushima accident site describing the technical solution conceived developed and deployed at Fukushima NPP for the process control of the treatment system of contaminated water. A detailed description of all levels design choices, from detection technologies to system architecture is offer in the paper as well as the read-out and global data management system. This paper describes also the technical choices executed and put in place to overcome the challenges related to the high radiological contamination on site. (authors)

Advances in nuclear science and technology

CERN Document Server

Henley, Ernest J

1976-01-01

Advances in Nuclear Science and Technology, Volume 9 provides information pertinent to the fundamental aspects of nuclear science and technology. This book discusses the safe and beneficial development of land-based nuclear power plants.Organized into five chapters, this volume begins with an overview of the possible consequences of a large-scale release of radioactivity from a nuclear reactor in the event of a serious accident. This text then discusses the extension of conventional perturbation techniques to multidimensional systems and to high-order approximations of the Boltzmann equation.

Advances in nuclear science and technology

CERN Document Server

Henley, Ernest J

1972-01-01

Advances in Nuclear Science and Technology, Volume 6 provides information pertinent to the fundamental aspects of nuclear science and technology. This book covers a variety of topics, including nuclear steam generator, oscillations, fast reactor fuel, gas centrifuge, thermal transport system, and fuel cycle.Organized into six chapters, this volume begins with an overview of the high standards of technical safety for Europe's first nuclear-propelled merchant ship. This text then examines the state of knowledge concerning qualitative results on the behavior of the solutions of the nonlinear poin

Preliminary Conceptual Design and Development of Core Technology of Very High Temperature Gas-Cooled Reactor Hydrogen Production

Energy Technology Data Exchange (ETDEWEB)

Chang, Jong Hwa; Kang, H. S.; Gil, C. S. and others

2006-05-15

For the nuclear hydrogen production system, the VHTR technology and the IS cycle technology are being developed. A comparative evaluation on the block type reactor and the pebble type reactor is performed to decide a proper nuclear hydrogen production reactor. 100MWt prismatic type reactor is tentatively decided and its safety characteristics are roughly investigated. Computation codes of nuclear design, thermo-fluid design, safety-performance analysis are developed and verified. Also, the development of a risk informed design technology is started. Experiments for metallic materials and graphites are carried out for the selection of materials of VHTR components. Diverse materials for process heat exchanger are studied in various corrosive environments. Pyrolytic carbon and SiC coating technology is developed and fuel manufacturing technology is basically established. Computer program is developed to evaluate the performance of coated particle fuels.

Preliminary Conceptual Design and Development of Core Technology of Very High Temperature Gas-Cooled Reactor Hydrogen Production

International Nuclear Information System (INIS)

Chang, Jong Hwa; Kang, H. S.; Gil, C. S. and others

2006-05-01

For the nuclear hydrogen production system, the VHTR technology and the IS cycle technology are being developed. A comparative evaluation on the block type reactor and the pebble type reactor is performed to decide a proper nuclear hydrogen production reactor. 100MWt prismatic type reactor is tentatively decided and its safety characteristics are roughly investigated. Computation codes of nuclear design, thermo-fluid design, safety-performance analysis are developed and verified. Also, the development of a risk informed design technology is started. Experiments for metallic materials and graphites are carried out for the selection of materials of VHTR components. Diverse materials for process heat exchanger are studied in various corrosive environments. Pyrolytic carbon and SiC coating technology is developed and fuel manufacturing technology is basically established. Computer program is developed to evaluate the performance of coated particle fuels

Maintaining a technology-neutral approach to hydrogen production process development through conceptual design of the next generation nuclear plant - HTR2008-58191

International Nuclear Information System (INIS)

Patterson, M. W.; Park, C. V.

2008-01-01

The Energy Policy Act of 2005 (EPAct) charges the Dept. of Energy (DOE) with developing and demonstrating the technical and economic feasibility of using high temperature gas-cooled reactor (HTGR) technology for the production of electricity and/or hydrogen. The design, construction and demonstration of this technology in an HTGR proto-type reactor are termed the Next Generation Nuclear Plant (NGNP) Project. Currently, parallel development of three hydrogen production processes will continue until a single process technology is recommended for final demonstration in the NGNP - a technology neutral approach. This analysis compares the technology neutral approach to acceleration of the hydrogen process down-selection at the completion of the NGNP conceptual design to improve integration of the hydrogen process development and NGNP Project schedule. The accelerated schedule activities are based on completing evaluations and achieving technology readiness levels (TRLs) identified in NGNP systems engineering and technology road-maps. The cost impact of accelerating the schedule and risk reduction strategies was also evaluated. The NGNP Project intends to design and construct a component test facility (CTF) to support testing and demonstration of HTGR technologies, including those for hydrogen production. The demonstrations will support scheduled design and licensing activities, leading to subsequent construction and operation of the NGNP. Demonstrations in the CTF are expected to start about two years earlier than similarly scaled hydrogen demonstrations planned in the technology neutral baseline. The schedule evaluation assumed that hydrogen process testing would be performed in the CTF and synchronized the progression of hydrogen process development with CTF availability. (authors)

International Nuclear Science and Technology Conference 2016

International Nuclear Information System (INIS)

2017-01-01

Conference Nuclear technology has played an important role in many aspects of our lives, including agriculture, medicine and healthcare, materials, environment, forensics, energy, and frontier advancement. The International Nuclear Science and Technology Conference (INST) aims to bring together scientists, engineers, academics and students to share knowledge and experiences about all aspects of nuclear sciences. INST2016 was the second of the INST conference series organized by Thailand Institute of Nuclear Technology. INST has evolved from a national conference series on nuclear science and technology that was held every two years in Bangkok for over a twenty-year period. INST2016 was held from 4 - 6 August 2016 in Bangkok, Thailand, under the central theme “Nuclear for Better Life”. The conference working language was English. The oral and poster research presentations covered seven major topics: • Nuclear physics and engineering (PHY) • Nuclear and radiation safety (SAF) • Medical and nutritional applications (MED) • Environmental applications (ENV) • Radiation processing and industrial applications (IND) • Agriculture and food applications (AGR) • Instrumentation and other related topics (INS) The welcome addresses, committees, program of the conference and the list of presentations can be found in the PDF. (paper)

Nuclear Technology Review 2013. Report by the Director General

International Nuclear Information System (INIS)

2013-01-01

In response to requests by Member States, the Secretariat produces a comprehensive Nuclear Technology Review each year. Attached is this year's report, which highlights notable developments principally in 2012. The Nuclear Technology Review 2013 covers the following areas: power applications, atomic and nuclear data, accelerators and research reactors, and nuclear sciences and applications. Additional documentation associated with the Nuclear Technology Review 2013 is available on the Agency's website1 in English on nuclear hydrogen production technology and preliminary lessons learned from the Fukushima Daiichi accident for advanced nuclear power plant technology development. Information on the IAEA's activities related to nuclear science and technology can also be found in the IAEA's Annual Report 2012 (GC(57)/3), in particular the Technology section, and the Technical Cooperation Report for 2012 (GC(57)/INF/4). The document has been modified to take account, to the extent possible, of specific comments by the Board of Governors and other comments received from Member States. (author)

A study on the nuclear technology policy

International Nuclear Information System (INIS)

Yang, M. H.; Kim, H. J.; Chung, W. S.; Lee, T. J.; Yun, S. W.; Jeong, Ik

2002-01-01

This study was carried out as a part of institutional activities of KAERI. This study suggested the effective and systematic alternatives for the development of domestic industry through nuclear long-term R and D program while timely responding to the environmental change in local and global sense. First of all, this study investigated the current status and prospect of nuclear power supply, the global technological change of nuclear fuel cycle, the nuclear policy changes of major countries and the role of nuclear energy in East Asian countries. Second, some policy alternatives are suggested in association with the role of national R and D in enhancing industrial competitiveness, the effective management of nuclear long-term R and D program to facilitate technological innovation and the way to enlarge the utilization of nuclear R and D results and radiation technology

The transfer of nuclear technology: necessities and limitations

International Nuclear Information System (INIS)

Haunschild, H.-H.

1978-01-01

Political and economical importance of the transfer of nuclear technologies to less developed countries is examined. Energy needs of the world create the necessity of technology transfer. Three levels are distinguished: 1) Basic elements of cooperation are agreed between the two Governments, 2) scientific cooperation and 3) industrial cooperation. Technology transfer is more than mere technology export. Limitations of nuclear technology transfer are: the lack of infrastructure, the high price of a nuclear power station but above all the problem of proliferation. In conclusion the solution of international problems of nuclear energy is the concept of cooperation on the basis of equal rights

Decontamination Technology Development for Nuclear Research Facilities

International Nuclear Information System (INIS)

Oh, Won Zin; Jung, Chong Hun; Choi, Wang Kyu; Won, Hui Jun; Kim, Gye Nam

2004-02-01

Technology development of surface decontamination in the uranium conversion facility before decommissioning, technology development of component decontamination in the uranium conversion facility after decommissioning, uranium sludge treatment technology development, radioactive waste soil decontamination technology development at the aim of the temporary storage soil of KAERI, Optimum fixation methodology derivation on the soil and uranium waste, and safety assessment methodology development of self disposal of the soil and uranium waste after decontamination have been performed in this study. The unique decontamination technology applicable to the component of the nuclear facility at room temperature was developed. Low concentration chemical decontamination technology which is very powerful so as to decrease the radioactivity of specimen surface under the self disposal level was developed. The component decontamination technology applicable to the nuclear facility after decommissioning by neutral salt electro-polishing was also developed. The volume of the sludge waste could be decreased over 80% by the sludge waste separation method by water. The electrosorption method on selective removal of U(VI) to 1 ppm of unrestricted release level using the uranium-containing lagoon sludge waste was tested and identified. Soil decontamination process and equipment which can reduce the soil volume over 90% were developed. A pilot size of soil decontamination equipment which will be used to development of real scale soil decontamination equipment was designed, fabricated and demonstrated. Optimized fixation methodology on soil and uranium sludge was derived from tests and evaluation of the results. Safety scenario and safety evaluation model were development on soil and uranium sludge aiming at self disposal after decontamination

Can nuclear power be enough for future technology?

International Nuclear Information System (INIS)

Serizawa, Akimi

2017-01-01

This paper focused on the report 'Can nuclear power be future technology?' published on September 28, 2008 by the Leading R and D Committee of Japan Society for the Promotion of Science. It took up part of the discussions at the general discussion session, and those of two working groups mainly by young committee members, and summarized and compiled them. Regarding 'maturity of nuclear technology as future technology,' this paper summarized and discussed from the technical viewpoint the current situation and problems of nuclear power in consideration of the future. Major topics include (1) nuclear safety and disaster prevention, (2) decommissioning of rectors (normal reactors, and accident reactors), (3) back end, (4) effects of low-level radiation, (5) technology trends, (6) economic efficiency, and (7) human resource development. Regarding 'social acceptability of nuclear energy,' the following were discussed: (1) basic human rights such as 'moral rights' and nuclear technologies, (2) risk communication and its problems, and (3) measures to improve the reliability of stakeholders involved in nuclear power. Regarding 'nuclear accident responding team,' this paper covered the nuclear accident responding unit founded in France after the nuclear accident in Japan, and nuclear accident responding unit founded in Japan. (A.O.)

Analysis on Japanese nuclear industrial technologies and their military implications

Energy Technology Data Exchange (ETDEWEB)

Kim, H S; Yang, M H; Kim, H J. and others

2000-10-01

This study covered the following scopes : analysis of Japan's policy trend on the development and utilization of nuclear energy, international and domestic viewpoint of Japan's nuclear weapon capability, Japan's foreign affairs and international cooperation, status of Japan's nuclear technology development and its level, status and level of nuclear core technologies such as nuclear reactor and related fuel cycle technologies. Japan secures the whole spectrum of nuclear technologies including core technologies through the active implementation of nuclear policy for the peaceful uses of nuclear energy during the past five decades. Futhermore, as the result of the active cultivation of nuclear industry, Japan has most nuclear-related facilities and highly advanced nuclear industrial technologies. Therefore, it is reasonable that Japan might be recognized as one of countries having capability to get nuclear capability in several months.

Analysis on Japanese nuclear industrial technologies and their military implications

International Nuclear Information System (INIS)

Kim, H. S.; Yang, M. H.; Kim, H. J. and others

2000-10-01

This study covered the following scopes : analysis of Japan's policy trend on the development and utilization of nuclear energy, international and domestic viewpoint of Japan's nuclear weapon capability, Japan's foreign affairs and international cooperation, status of Japan's nuclear technology development and its level, status and level of nuclear core technologies such as nuclear reactor and related fuel cycle technologies. Japan secures the whole spectrum of nuclear technologies including core technologies through the active implementation of nuclear policy for the peaceful uses of nuclear energy during the past five decades. Futhermore, as the result of the active cultivation of nuclear industry, Japan has most nuclear-related facilities and highly advanced nuclear industrial technologies. Therefore, it is reasonable that Japan might be recognized as one of countries having capability to get nuclear capability in several months

Research on process management of nuclear power technological innovation

International Nuclear Information System (INIS)

Yang Hua; Zhou Yu

2005-01-01

Different from the other technological innovation processes, the technological innovation process of nuclear power engineering project is influenced deeply by the extensive environmental factors, the technological innovation of nuclear power engineering project needs to make an effort to reduce environmental uncertainty. This paper had described the mechanism of connection technological innovation process of nuclear power engineering project with environmental factors, and issued a feasible method based on model of bargaining to incorporate technological innovation process management of nuclear power engineering project with environmental factors. This method has realistic meanings to guide the technological innovation of nuclear power engineering project. (authors)

Implementation digital technologies in nuclear utilities

Energy Technology Data Exchange (ETDEWEB)

Wiegand, C.; Maselli, A.J., E-mail: Tony.Maselli@Invensys.com [Invensys Operations Management, London (United Kingdom)

2012-07-01

The introduction of digital technologies into the nuclear industry has assisted in many ways and made many of the Life Extensions and Uprates a possibility. But with this introduction of digital technologies comes some potentially challenging issues which need to be addressed for ultimate project success. This presentation discusses what a nuclear utility should consider and establish when implementing digital technologies in their plant. Digital technologies have been employed in many safety critical industries such as Aerospace, Pharmaceutical, Oil and Gas, and Chemical. However, nuclear industry implementation of digital technologies has been slow and in many ways tenuous. There are even documented operating experience events in which plant trips/SCRAMs occurred during a digital system implementation. This presentation aims to prevent those issues drawing upon the lessons learned over the past 5 years. Considerations include general challenges to overcome when implementing Digital Technologies, how to justify and execute projects, evaluation of resource knowledge, and the new challenges of Cyber Security. (author)

Implementation digital technologies in nuclear utilities

International Nuclear Information System (INIS)

Wiegand, C.; Maselli, A.J.

2012-01-01

The introduction of digital technologies into the nuclear industry has assisted in many ways and made many of the Life Extensions and Uprates a possibility. But with this introduction of digital technologies comes some potentially challenging issues which need to be addressed for ultimate project success. This presentation discusses what a nuclear utility should consider and establish when implementing digital technologies in their plant. Digital technologies have been employed in many safety critical industries such as Aerospace, Pharmaceutical, Oil and Gas, and Chemical. However, nuclear industry implementation of digital technologies has been slow and in many ways tenuous. There are even documented operating experience events in which plant trips/SCRAMs occurred during a digital system implementation. This presentation aims to prevent those issues drawing upon the lessons learned over the past 5 years. Considerations include general challenges to overcome when implementing Digital Technologies, how to justify and execute projects, evaluation of resource knowledge, and the new challenges of Cyber Security. (author)

Nuclear Systems (NS): Technology Demonstration Unit (TDU)

Data.gov (United States)

National Aeronautics and Space Administration — The Nuclear Systems Project demonstrates nuclear power technology readiness to support the goals of NASA's Space Technology Mission Directorate. To this end, the...

Nuclear power plant functions: overview, maintenance, design practices, training

International Nuclear Information System (INIS)

Gray, J.

1984-01-01

The author gives a history of the nuclear industry in the US beginning with the Atoms for Peace Proposal in 1954 and summarizes the nuclear industry's importance in the realm of electric power production today. The primary problems facing the domestic nuclear industry are identified as the lengthening schedules for plant licensing and construction, and the associated uncertainty in plant costs and difficulty in financing, and the erosion of public confidence. Views on technological approaches to the future of nuclear power and the role regulation will play in the future as a fundamental force are discusses in the paper. Also discussed are the importance of standardization of advanced reactor designs and quality assurance

Fundamental Technology Development for Radiation Damage in Nuclear Materials

International Nuclear Information System (INIS)

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

2005-04-01

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

Kazakhstan innovation projects in nuclear technologies field

International Nuclear Information System (INIS)

Shkol'nik, V.S.; Tukhvatulin, Sh.T.

2005-01-01

At present in the Republic of Kazakhstan in preparation and realization stage there are several innovation projects related with use of advanced nuclear technologies. Projects are as follows: 'Implementation of Kazakhstan thermonuclear reactor tokamak (KTM)'; 'Implementation at the L.N. Gumilev Eurasian National University the inter-disciplinary research complex on the heavy ions accelerator base'; 'Development of the Technological Park 'Nuclear Technologies Center in Kurchatov city'; 'Development the first in the Central-Asian region Center of Nuclear Medicine and Biophysics'. The initiator and principal operator of these projects is the National Nuclear Center of the Republic of Kazakhstan

Quality assurance for the research and development of nuclear technology

International Nuclear Information System (INIS)

Yang, Myung Seung; Kim, Young Sea; Lee, In Koo

1990-01-01

Quality evaluation was carried to analyze the current status of QA activities in the various projects and to devise a proper measures for the improvement of quality system. KAERI QA program evaluation was also performed in cooperation with foreign QA experts (Nutech International, USA) to study the best QA system for KAERI which is performing various nuclear project ranging from nuclear design, manufacturing to basic researches. The acquisition of N-certificate and stamp from ASME (American Society of Mechanical Engineers) was successfully accomplished for the quality system of power reactor system design. The basic study on the QA in R and D, computerization of quality evaluation system was also performed to upgrade the safety and reliability of nuclear projects by the utilization of these advanced quality technologies. (author)

Nuclear technology. All in good hands

International Nuclear Information System (INIS)

Mueller, Michaela

2011-01-01

Babcock Noell GmbH (BNG) has more than 40 years of practical experience and fundamental know-how in the field of nuclear technology and thus is well equipped to meet future challenges. This applies to building new nuclear power plants, upgrading and decommissioning existing facilities as well as to conditioning and storage of radioactive waste. BNG is a supplier of, among other things, components for machine technology, personnel and materials transfer locks, safety enclosures and pool liners. Outstanding, technically demanding reference projects have demonstrated BNG's capabilities. BNG is a reliable service and assembly partner to the operators of nuclear power plants and nuclear facilities. This sector of activities has as its backbone a separate team of experienced service and assembly personnel. The synergies of engineering and service competence intensively utilized by Babcock Noell GmbH are employed, inter alia, in the development and advanced development, respectively, of nuclear technology products fit for practical use, such as personnel and materials transfer locks. (orig.)

Topics on Japanese aseismic design for nuclear installations

International Nuclear Information System (INIS)

Nakamura, Masahiko

2002-01-01

Major items of of Japanese anti-seismic design for nuclear installations involve three topics: earthquakes and ground motion; seismic design and safety evaluation. The first topic deal with: improvement of geological survey technology, evaluation of ground motion from active faults, and characterisation of earthquake from individual faults. Seismic design involves: evaluation of design ground motion (spectra), classification of structures, systems and components (SSCs) based on the seismic importance, and seismic design criteria and critical loads. Safety evaluation of seismic PSA is dependent on the consistency of the the two previous items. Seismic hazard evaluation methodology, database and examples of analysis are described. Analysis method using fault model is included

Analysis on Japanese nuclear industrial technologies and their military implications

Energy Technology Data Exchange (ETDEWEB)

Kim, H. S.; Yang, M. H.; Kim, H. J. and others

2000-10-01

This study covered the following scopes : analysis of Japan's policy trend on the development and utilization of nuclear energy, international and domestic viewpoint of Japan's nuclear weapon capability, Japan's foreign affairs and international cooperation, status of Japan's nuclear technology development and its level, status and level of nuclear core technologies such as nuclear reactor and related fuel cycle technologies. Japan secures the whole spectrum of nuclear technologies including core technologies through the active implementation of nuclear policy for the peaceful uses of nuclear energy during the past five decades. Futhermore, as the result of the active cultivation of nuclear industry, Japan has most nuclear-related facilities and highly advanced nuclear industrial technologies. Therefore, it is reasonable that Japan might be recognized as one of countries having capability to get nuclear capability in several months.

Chemistry and nuclear technology

International Nuclear Information System (INIS)

De Wet, W.J.

1977-01-01

The underlying principles of nuclear sciece and technology as based on the two basic phenomena, namely, radioactivity and nuclear reactions, with their relatively large associated energy changes, are outlined. The most important contributions by chemists in the overall historical development are mentioned and the strong position chemistry has attained in these fields is indicated. It is concluded that chemistry as well as many other scientific discplines (apart from general benefits) have largely benefitted from these nuclear developments [af

Proceeding of the 7. Seminar on Technology and Safety of Nuclear Power Plants and Nuclear Facilities

International Nuclear Information System (INIS)

Hastowo, Hudi; Antariksawan, Anhar R.; Soetrisnanto, Arnold Y; Jujuratisbela, Uju; Aziz, Ferhat; Su'ud, Zaki; Suprawhardana, M. Salman

2002-02-01

The seventh proceedings of seminar safety and technology of nuclear power plant and nuclear facilities, held by National Nuclear Energy Agency. The Aims of seminar is to exchange and disseminate information about safety and nuclear Power Plant Technology and Nuclear Facilities consist of technology; high temperature reactor and application for national development sustain able and high technology. This seminar level all aspects technology, Power Reactor research reactor, high temperature reactor and nuclear facilities. The article is separated by index

Technology in the policy process - controlling nuclear power

International Nuclear Information System (INIS)

Collingridge, D.

1983-01-01

The discussion in this book is built around nuclear power. The technology of nuclear power is shown to have features which make it inflexible in the sense that, once built, it is difficult and expensive to control. If inflexible technology is to be avoided, it is crucially important to be able to identify this failing at an early stage in the technology's development, before it has acquired an immunity to political control. Again, this problem is approached through the example of nuclear power, in particular the breeder reactor. The breeder is shown to be even less flexible than today's nuclear technology, because it will have higher capital costs, be of greater capital intensity, longer lead time, larger unit size, and will require more infrastructure for its operation. If this is developed, the breeder will be even less open to political control than the nuclear plant of the present. To put it another way, its planning will be even more open to errors and whatever errors are made will be even more costly than for existing nuclear technology. It is therefore even less of a socially and economically acceptable technology than today's nuclear power. (author)

Advanced technology for nuclear powerplants

International Nuclear Information System (INIS)

Rohm, H.H.

1987-01-01

Advanced technology offers significant potential benefit to the nuclear industry. Improvements can be anticipated in plant performance, reliability, and overall plant safety as well as reduced life cycle costs. Utilizing artificial intelligence and expert systems, robotics, advanced instruments and controls, and modularization technologies can enhance plant operations and provide new insights and perspectives to plant risk and thus focus resources to areas of importance. Plant reliability, operability, availability, accident interdiction and limitation, and plant recovery are expected to improve. However, utilizing these technologies is not an automatic process. In addition to the actual costs associated with developing and implementing the technologies, operator training and acceptance represents a potential significant problem. Traditional plant operators have little or no experience with computer technology. There has already been some difficulty getting nuclear plant operators to accept and use the new technologies that have been implemented to accept and use the new technologies that have been implemented thus far

Enabling Technologies for Ultra-Safe and Secure Modular Nuclear Energy

International Nuclear Information System (INIS)

Mendez Cruz, Carmen Margarita; Rochau, Gary E.; Middleton, Bobby; Rodriguez, Salvador B.; Rodriguez, Carmelo; Schleicher, Robert

2016-01-01

Sandia National Laboratories and General Atomics are pleased to respond to the Advanced Research Projects Agency-Energy (ARPA-e)'s request for information on innovative developments that may overcome various current reactor-technology limitations. The RFI is particularly interested in innovations that enable ultra-safe and secure modular nuclear energy systems. Our response addresses the specific features for reactor designs called out in the RFI, including a brief assessment of the current state of the technologies that would enable each feature and the methods by which they could be best incorporated into a reactor design.

Enabling Technologies for Ultra-Safe and Secure Modular Nuclear Energy

Energy Technology Data Exchange (ETDEWEB)

Mendez Cruz, Carmen Margarita [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Rochau, Gary E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Middleton, Bobby [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Rodriguez, Salvador B. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Rodriguez, Carmelo [General Atomics, San Diego, CA (United States); Schleicher, Robert [General Atomics, San Diego, CA (United States)

2016-06-01

Sandia National Laboratories and General Atomics are pleased to respond to the Advanced Research Projects Agency-Energy (ARPA-e)’s request for information on innovative developments that may overcome various current reactor-technology limitations. The RFI is particularly interested in innovations that enable ultra-safe and secure modular nuclear energy systems. Our response addresses the specific features for reactor designs called out in the RFI, including a brief assessment of the current state of the technologies that would enable each feature and the methods by which they could be best incorporated into a reactor design.

Innovative designs of nuclear reactors

International Nuclear Information System (INIS)

Gabaraev, B.A.; Cherepnin, Y.S.

2010-01-01

The world development scenarios predict at least a 2.5 time increase in the global consumption of primary energy in the first half of the twenty-first century. Much of this growth can be provided by the nuclear power which possesses important advantages over other energy technologies. However, the large deployment of nuclear sources may take place only when the new generation of reactors appears on the market and will be free of the shortcomings found in the existing nuclear power installations. The public will be more inclined to accept nuclear plants that have better economics; higher safety; more efficient management of the radioactive waste; lower risk of nuclear weapons proliferation, and provided that the focus is made on the energy option free of ∇ e 2 generation. Currently, the future of nuclear power is trusted to the technology based on fast reactors and closed fuel cycle. The latter implies reprocessing of the spent nuclear fuel of the nuclear plants and re-use of plutonium produced in power reactors

Impact of Nuclear Technology to the National Socio-Economy: Technical Support by Nuclear Malaysia

International Nuclear Information System (INIS)

Hazmimi Kasim; Ainul Hayati Daud; Jamal Khaer Ibrahim; Alawiah Musa

2011-01-01

In Malaysia, the development of nuclear technology began in the year 1972. More than 30 years of application, today, the technology made impact to the national socio-economy through contribution to GDP and; improving quality of life and enhanced societal well-being. The application of nuclear technology both in public and private agencies in industrial, medical and agricultural sectors were considered. In 2008, the impact of nuclear technology shows the contribution of 0.032% to the total GDP. Industry sector shows an increasing trend and is the highest contributor, while agriculture sector remains the lowest. In this regard, Malaysian Nuclear Agency (Nuclear Malaysia) played an important role as a technical support agency in nuclear technology, as a supplier and provider for the service, training and research for the industrial, medical and agricultural sectors. (author)

Where is high technology taking nuclear medicine

International Nuclear Information System (INIS)

Veall, N.

1985-01-01

The question is posed as to whether high technology in nuclear medicine might lead to the nuclear medicine practitioner possibly finishing up working for the machine rather than the improvement of health care in its widest sense. A brief examination of some pros and cons of high technology nuclear medicine is given. (U.K.)

Safety management in nuclear technology. Proceedings

International Nuclear Information System (INIS)

2008-01-01

At the symposium of TueV Sued AG (Munich, Federal Republic of Germany) held in Munich on 28 and 29 October 2008, the following lectures were held: (1) Fundamental requirements of the management system in nuclear technology - Experiences from the international developments at IAEA and WENRA (M. Herttrich); (2) Information from a comparison of requirements of safety management systems (B. Kallenbach-Herbert); (3) Requirements of a modern management system in German nuclear power plants from the view of nuclear safety (D. Majer); (4) Requirements on safety management in module 8 of the regulations project (M. Maqua); (5) Requirements on the management system in nuclear power plants according to GRS-229 and developments at the KTA 1402 ''Integrated management system for safe operation of nuclear power plants (in progress)'' (C. Verstegen); (6) Experiences from the development and implementation of safety management systems in connection with the works management of a nuclear power plant (K. Ramler); (7) Design of a safety management system of a nuclear power plant in consideration of existing management systems (U. Naumann); (8) Experiences in the utilization and evaluation of a safety management system (J. Ritter); (9) Aspects of leadership of safety management systems (S. Seitz); (10) Management of safety or safety management system? Prevailing or administration? (A. Frischknecht); (11) Change management - strategies for successful transfer of new projects: How can I motivate co-workers for a further development of the safety management system? (U. Schnabel); (12) Requirements concerning indicators in integrated management systems and safety management systems (J. Stiller); (13) Integration of proactive and reactive indicators in the safety management system (B. Fahlbruch); (14) What do indicators show? About the use of indicators by regulatory authorities (A. Kern); (15) Safety management and radiation protection in nuclear technology (K. Grantner); (16) Any more

Design and Test Plans for a Non-Nuclear Fission Power System Technology Demonstration Unit

Science.gov (United States)

Mason, Lee; Palac, Donald; Gibson, Marc; Houts, Michael; Warren, John; Werner, James; Poston, David; Qualls, Arthur Lou; Radel, Ross; Harlow, Scott

2012-01-01

A joint National Aeronautics and Space Administration (NASA) and Department of Energy (DOE) team is developing concepts and technologies for affordable nuclear Fission Power Systems (FPSs) to support future exploration missions. A key deliverable is the Technology Demonstration Unit (TDU). The TDU will assemble the major elements of a notional FPS with a non-nuclear reactor simulator (Rx Sim) and demonstrate system-level performance in thermal vacuum. The Rx Sim includes an electrical resistance heat source and a liquid metal heat transport loop that simulates the reactor thermal interface and expected dynamic response. A power conversion unit (PCU) generates electric power utilizing the liquid metal heat source and rejects waste heat to a heat rejection system (HRS). The HRS includes a pumped water heat removal loop coupled to radiator panels suspended in the thermal-vacuum facility. The basic test plan is to subject the system to realistic operating conditions and gather data to evaluate performance sensitivity, control stability, and response characteristics. Upon completion of the testing, the technology is expected to satisfy the requirements for Technology Readiness Level 6 (System Demonstration in an Operational and Relevant Environment) based on the use of high-fidelity hardware and prototypic software tested under realistic conditions and correlated with analytical predictions.

U.S. FUEL CYCLE TECHNOLOGIES R&D PROGRAM FOR NEXT GENERATION NUCLEAR MATERIALS MANAGEMENT

Directory of Open Access Journals (Sweden)

M.C. MILLER

2013-11-01

Full Text Available The U.S. Department of Energy's Fuel Cycle Technologies R&D program under the Office of Nuclear Energy is working to advance technologies to enhance both the existing and future fuel cycles. One thrust area is in developing enabling technologies for next generation nuclear materials management under the Materials Protection, Accounting and Control Technologies (MPACT Campaign where advanced instrumentation, analysis and assessment methods, and security approaches are being developed under a framework of Safeguards and Security by Design. An overview of the MPACT campaign's activities and recent accomplishments is presented along with future plans.

Technological development of Guangdong nuclear power station

International Nuclear Information System (INIS)

Huang Shiqiang

2000-01-01

After over 5 years of operations, the Guangdong Nuclear Power Station (GNPS) has achieved good results both economically and in operational safety performance. The main attributes to the success of the plant operational performances include the equipment reliability, the technical capability and management efficiency. To that the key strategy has been to adopt know-how and technological transfer and encourage self-innovation, aiming to strive for the long-term self-reliance in design, manufacturing and operating the plant. (author)

Technology Roadmap on Instrumentation, Control, and Human-Machine Interface to Support DOE Advanced Nuclear Energy Programs

International Nuclear Information System (INIS)

Donald D Dudenhoeffer; Burce P Hallbert

2007-01-01

Instrumentation, Controls, and Human-Machine Interface (ICHMI) technologies are essential to ensuring delivery and effective operation of optimized advanced Generation IV (Gen IV) nuclear energy systems. In 1996, the Watts Bar I nuclear power plant in Tennessee was the last U.S. nuclear power plant to go on line. It was, in fact, built based on pre-1990 technology. Since this last U.S. nuclear power plant was designed, there have been major advances in the field of ICHMI systems. Computer technology employed in other industries has advanced dramatically, and computing systems are now replaced every few years as they become functionally obsolete. Functional obsolescence occurs when newer, more functional technology replaces or supersedes an existing technology, even though an existing technology may well be in working order. Although ICHMI architectures are comprised of much of the same technology, they have not been updated nearly as often in the nuclear power industry. For example, some newer Personal Digital Assistants (PDAs) or handheld computers may, in fact, have more functionality than the 1996 computer control system at the Watts Bar I plant. This illustrates the need to transition and upgrade current nuclear power plant ICHMI technologies

Nuclear technology review 2006

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-08-15

While the current outlook for nuclear power remains mixed, 2005 was a year of rising expectations. In March, high level representatives of 74 governments, including 25 representatives at the ministerial level, gathered in Paris at a conference organized by the IAEA to consider the future role of nuclear power. The vast majority of participants affirmed that nuclear power can make a major contribution to meeting energy needs and sustaining the world's development in the 21st century for a large number of both developed and developing countries. Rising expectations are driven by nuclear power's performance record, by growing energy needs around the world coupled with rising oil and natural gas prices, by environmental constraints, by concerns about energy supply security in a number of countries, and by ambitious expansion plans in several countries. There were 441 nuclear power plants in operation as of 31 December 2005 and 27 under construction. Four new nuclear power plants were connected to the grid in 2005 (two in Japan and one each in India and the Republic of Korea), and one laid-up plant was reconnected in Canada. There were two nuclear power plant retirements, both in accordance with national nuclear phase-out policies.There were three construction starts, Lingao-3 in China, Olkiluoto-3 in Finland and Chasnupp-2 in Pakistan. Olkiluoto-3 is the first new construction in Western Europe since 1991. Asia remains the centre of expansion, accounting for 16 of the 27 reactors under construction at the end of 2005, and for 24 of the last 34 reactors to have been connected to the grid. National research on advanced reactor designs continues for all reactor categories: water cooled, gas cooled, liquid metal cooled, and hybrid systems. A major advance in fusion energy occurred in June 2005 with the signing of the joint declaration of all parties to the negotiations on the International Thermonuclear Experimental Reactor (ITER) and the agreement to start construction at

Nuclear technology review 2006

International Nuclear Information System (INIS)

2006-08-01

While the current outlook for nuclear power remains mixed, 2005 was a year of rising expectations. In March, high level representatives of 74 governments, including 25 representatives at the ministerial level, gathered in Paris at a conference organized by the IAEA to consider the future role of nuclear power. The vast majority of participants affirmed that nuclear power can make a major contribution to meeting energy needs and sustaining the world's development in the 21st century for a large number of both developed and developing countries. Rising expectations are driven by nuclear power's performance record, by growing energy needs around the world coupled with rising oil and natural gas prices, by environmental constraints, by concerns about energy supply security in a number of countries, and by ambitious expansion plans in several countries. There were 441 nuclear power plants in operation as of 31 December 2005 and 27 under construction. Four new nuclear power plants were connected to the grid in 2005 (two in Japan and one each in India and the Republic of Korea), and one laid-up plant was reconnected in Canada. There were two nuclear power plant retirements, both in accordance with national nuclear phase-out policies.There were three construction starts, Lingao-3 in China, Olkiluoto-3 in Finland and Chasnupp-2 in Pakistan. Olkiluoto-3 is the first new construction in Western Europe since 1991. Asia remains the centre of expansion, accounting for 16 of the 27 reactors under construction at the end of 2005, and for 24 of the last 34 reactors to have been connected to the grid. National research on advanced reactor designs continues for all reactor categories: water cooled, gas cooled, liquid metal cooled, and hybrid systems. A major advance in fusion energy occurred in June 2005 with the signing of the joint declaration of all parties to the negotiations on the International Thermonuclear Experimental Reactor (ITER) and the agreement to start construction at

Waste disposal technologies: designs and evaluations

International Nuclear Information System (INIS)

Shaw, R.A.

1987-01-01

Many states and compacts are presently in the throes of considering what technology to select for their low level waste disposal site. Both the technical and economic aspects of disposal technology are important considerations in these decisions. It is also important that they be considered in the context of the entire system. In the case of a nuclear power plant, that system encompasses the various individual waste streams that contain radioactivity, the processing equipment which reduces the volume and/or alters the form in which the radioisotopes are contained, the packaging of the processed wastes in shipment, and finally its disposal. One further part of this is the monitoring that takes place in all stages of this operation. This paper discusses the results of some research that has been sponsored by EPRI with the principal contractor being Rogers and Associates Engineering Corporation. Included is a description of the distinguishing features found in disposal technologies developed in a generic framework, designs for a selected set of these disposal technologies and the costs which have been derived from these designs. In addition, a description of the early efforts towards defining the performance of these various disposal technologies is described. 5 figures, 1 table

Status and trends in nuclear technology for power plants with WWER-1000 reactors. Review

Energy Technology Data Exchange (ETDEWEB)

Zorev, N N

1977-04-01

The problems of improving quality of nuclear equipment for WWER-1000 power plants and associated nuclear technology automation are surveyed. Examples of technological innovations are presented which significantly reduce labour intensity, time consumption and increase quality standards of the products. Some new automated equipments for materials welding, working, machining and quality control are described. The discussion is centering around heavy-section steel technologies. Some mechanical properties of new-developed nuclear grade steels designed for producing reactor vessels and steamgenerators, volume compensators and pipes, as well as steam separators and steamsuperheaters are also presented. Their properties (impact strength and radiation resistance) are pointed out to be superior to that of steels used abroad. The basic trend in nuclear structural material developments is towards integrated optimization of strength, performance and workability.

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

Energy Technology Data Exchange (ETDEWEB)

Richard Metcalf; Robert Bean

2009-10-01

Executive Summary The International Atomic Energy Agency (IAEA) implements nuclear safeguards and verifies countries are compliant with their international nuclear safeguards agreements. One of the key provisions in the safeguards agreement is the requirement that the country provide nuclear facility design and operating information to the IAEA relevant to safeguarding the facility, and at a very early stage. , This provides the opportunity for the IAEA to verify the safeguards-relevant features of the facility and to periodically ensure that those features have not changed. The national authorities (State System of Accounting for and Control of Nuclear Material - SSAC) provide the design information for all facilities within a country to the IAEA. The design information is conveyed using the IAEA’s Design Information Questionnaire (DIQ) and specifies: (1) Identification of the facility’s general character, purpose, capacity, and location; (2) Description of the facility’s layout and nuclear material form, location, and flow; (3) Description of the features relating to nuclear material accounting, containment, and surveillance; and (4) Description of existing and proposed procedures for nuclear material accounting and control, with identification of nuclear material balance areas. The DIQ is updated as required by written addendum. IAEA safeguards inspectors examine and verify this information in design information examination (DIE) and design information verification (DIV) activities to confirm that the facility has been constructed or is being operated as declared by the facility operator and national authorities, and to develop a suitable safeguards approach. Under the Next Generation Safeguards Initiative (NGSI), the National Nuclear Security Administrations (NNSA) Office of Non-Proliferation and International Security identified the need for more effective and efficient verification of design information by the IAEA for improving international safeguards

Nuclear facilities: repair and replacement technologies

International Nuclear Information System (INIS)

2005-01-01

The oldest operating reactors are more than 35 years old and are now facing major maintenance operations. The first replacement of a pressurizer took place in autumn 2005 at the St-Lucie plant (Usa) while steam generators have been currently replaced since 1983. Nuclear industry has to adapt to this new market by proposing innovative technological solutions in the reactor maintenance field. This document gathers the 9 papers presented at the conference. The main improvements concern repair works on internal components of PWR-type reactors, the replacement of major components of the primary coolant circuit and surface treatments to limit the propagation of damages. The first paper shows that adequate design and feedback experience are good assets to manage the ageing of a nuclear unit. Another paper shows that a new repair method of a relief valve can avoid its replacement. (A.C.)

Development of System Engineering Technology for Nuclear Fuel Cycle

International Nuclear Information System (INIS)

Kim, Hodong; Choi, Iljae

2013-04-01

The development of efficient process for spent fuel and establishment of system engineering technology to demonstrate the process are required to develop nuclear energy continuously. The demonstration of pyroprocess technology which is proliferation resistance nuclear fuel cycle technology can reduce spent fuel and recycle effectively. Through this, people's trust and support on nuclear power would be obtained. Deriving the optimum nuclear fuel cycle alternative would contribute to establish a policy on back-end nuclear fuel cycle in the future, and developing the nuclear transparency-related technology would contribute to establish amendments of the ROK-U. S. Atomic Energy Agreement scheduled in 2014

China nuclear science and technology reports

International Nuclear Information System (INIS)

1987-01-01

114 abstracts of nuclear science and technology reports, which were published in 1986-1987 in China, are collected. The subjects inclucled are: nuclear physics, nuclear medicine, radiochemistry, isotopes and their applications, reactors and nuclear power plants, radioactive protection, nuclear instruments etc... They are arranged in accordance with the INIS subject categories, and a report number index is annexed

Legal aspects of the transfer of nuclear technology

International Nuclear Information System (INIS)

Sartorelli, C.

1980-03-01

The paper stresses the importance of nuclear technology transfer and describes the legal instruments for transfer of technical and scientific technology, particularly from the contractual viewpoint. A description follows of the setting-up of national joint ventures for nuclear power plant projects with emphasis on technological know-how to enable operation of plants in compliance with safety standards. The possibility is discussed of the export of nuclear technology, and finally mention is made of a proposal for a 'code of conduct' on such transfers in the framework of the United Nations, having regard to the 'London agreements' on nuclear exports. (NEA) [fr

The design of operating procedures manuals for nuclear power plants

International Nuclear Information System (INIS)

Bohr, E.; Preuss, W.; Reinartz, G.; Thau, G.

1977-03-01

This report describes the findings of a research on the desirable design of operating procedures manuals for nuclear power plants. The work was supported by a grant of the Federal Department of the Interior. Information was acquired from different sources. Interviews and discussions on manual design were carried out with manual users in nuclear power plants. Moreover, tasks carried out using procedures were either observed or, alternatively, the manner of using procedures was elicited by interviews. In addition, manual writers, managers from manufacturers and utilities, nuclear experts, and individuals involved in manual specification activities were interviewed. A major source of information has been the pertinent scientific and technical findings scattered in the literature on topics such as instructional technology, engineering psychology, psycholinguistics, and typography. A comprehensive bibliography is included. General rules are established on designing instructional material for use on the job, aiming at increasing their legability, comprehensibility, and suitability to guide human performance. The application of these rules to the design of individual operating procedures is demonstrated. Recommendations are given on the design, layout, development and implementation of manuals. (orig.) [de

Westinghouse AP600 advanced nuclear plant design

International Nuclear Information System (INIS)

Gangloff, W.

1999-01-01

As part of the cooperative US Department of Energy (DOE) Advanced Light Water Reactor (ALWR) Program and the Electric Power Research Institute (EPRI), the Westinghouse AP600 team has developed a simplified, safe, and economic 600-megawatt plant to enter into a new era of nuclear power generation. Designed to satisfy the standards set by DOE and defined in the ALWR Utility Requirements Document (URD), the Westinghouse AP600 is an elegant combination of innovative safety systems that rely on dependable natural forces and proven technologies. The Westinghouse AP600 design simplifies plant systems and significant operation, inspections, maintenance, and quality assurance requirements by greatly reducing the amount of valves, pumps, piping, HVAC ducting, and other complex components. The AP600 safety systems are predominantly passive, depending on the reliable natural forces of gravity, circulation, convection, evaporation, and condensation, instead of AC power supplies and motor-driven components. The AP600 provides a high degree of public safety and licensing certainty. It draws upon 40 years of experience in light water reactor components and technology, so no demonstration plant is required. During the AP600 design program, a comprehensive test program was carried out to verify plant components, passive safety systems components, and containment behavior. When the test program was completed at the end of 1994, the AP600 became the most thoroughly tested advanced reactor design ever reviewed by the US Nuclear Regulatory Commission (NRC). The test results confirmed the exceptional behavior of the passive systems and have been instrumental in facilitating code validations. Westinghouse received Final Design Approval from the NRC in September 1998. (author)

Dry Refabrication Technology Development of Spent Nuclear Fuel

International Nuclear Information System (INIS)

Lee, Jung Won; Park, G. I.; Park, C. J.

2010-04-01

Key technical data on advanced nuclear fuel cycle technology development for the spent fuel recycling have been produced in this study. In the frame work of DUPIC, dry process oxide products fabrication, hot cell experimental data for decladding, powdering and oxide product fabrication from low and high burnup spent fuel have been produced, basic technology for fabrication of spent fuel standard material has been developed, and remote modulated welding equipment has been designed and fabricated. In the area of advanced pre-treatment process development, a rotary-type oxidizer and spherical particle fabrication process were developed by using SIMFUEL and off-gas treatment technology and zircalloy tube treatment technology were studied. In the area of the property characteristics of dry process products, fabrication technology of simulated dry process products was established and property models were developed based on reproducible property measurement data

ASIC and HMC designs for portable nuclear instruments

International Nuclear Information System (INIS)

Chandratre, V.B.

2005-01-01

This paper describes the seed activity done so far for realizing the goal of compact portable nuclear instruments and related instrumentation that can be designed, developed and manufactured without external constraints. This important activity requires critical components to be made in the country by tapping and gearing the established industrial units for this activity. A good deal of ground work has been carried out over a period of time in setting up IC design facility and CAD-FAB interface. There has been a close interaction with the production and semiconductor facilities to design and develop ASIC, hybrids, display devices, detectors/sensors etc. Efforts are also undertaken to develop the critical technologies that are required to fulfill the requirement. A status report on various technologies, ASIC, hybrids and their application development done in the face of out-standing challenges is being presented here. (author)

Advanced nuclear power systems: Design, technology, safety and strategies for their deployment

International Nuclear Information System (INIS)

1994-01-01

The objectives of the symposium were to provide high level decision makers with an overview of the discussion concerning the need for nuclear power and salient features of advanced nuclear power systems; a forum for discussing the design objectives and safety approaches for such systems and the views of regulatory bodies; a forum for identifying barriers to the deployment of these systems and for reviewing strategies to overcome these barriers; and a forum for reviewing options for international cooperation in the development and deployment of such systems. Refs, figs and tabs

Status and trends of nuclear technologies - Report of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). Additional information (Companion CD-ROM)

International Nuclear Information System (INIS)

2009-09-01

The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was launched in the year 2000, based on a resolution by the IAEA General Conference (GC(44)/RES/21). INPRO intends to help to ensure that nuclear energy is available in the 21st century in a sustainable manner, and seeks to bring together all interested Member States, both technology holders and technology users, to consider, jointly, actions to achieve desired innovations. INPRO is taking care of the specific needs of developing countries. This IAEA publication is part of Phase 1 of INPRO. It intends to provide an overview on history, present situation and future perspectives of nuclear fuel cycle technologies. While this overview focuses on technical issues, nevertheless, the aspects of economics, environment, and safety and proliferation resistance are important background issues for this study. After a brief description about the INPRO project and an evaluation of existing and future reactor designs the publication covers nuclear fuel cycle issues in detail. It is expected that this documentation will provide IAEA Member States and their nuclear engineers and designers, as well as policy makers with useful information on status and trends of future nuclear fuel cycle technologies. Due to the size of the full report it was decided to attach a CD-ROM in the back of the summary report

International certification of nuclear power reactors design. A proposal from the U.S. NRC (Nuclear Regulatory Commission)

International Nuclear Information System (INIS)

Felizia, Eduardo R.

2006-01-01

The proposal foundations of the Nuclear Regulatory Commission Board Chairman are briefly described, which were enunciated at a meeting on Fourth Generation Reactors (Washington, March 2005). This proposal is analyzed mainly from the point of view of its consequences in third countries buyers of nuclear technology. The analysis is complemented by descriptions of the current process of the NRC design certification and of Third and Fourth Generation Reactors. (author) [es

Improvement of layout and piping design for PWR nuclear power plants

International Nuclear Information System (INIS)

Nozue, Kosei; Waki, Masato; Kashima, Hiroo; Yoshioka, Tsuyoshi; Obara, Ichiro.

1983-01-01

For a nuclear power plant, a period of nearly ten years is required from the initial planning stage to commencement of transmission after passing through the design, manufacturing, installation and trial running stages. In the current climate there is a trend that the time required for nuclear power plant construction will further increase when locational problems, thorough explanation to residents in the neighborhood of the construction site and their under-standing, subsequent safety checks and measures to be taken in compliance with various controls and regulations which get tighter year after year, are taken into account. Under such circumstances, in order to satisfy requirements such as improving the reliability of the nuclear power plant design, manufacturing and construction departments, improvements in the economy as well as the quality and shortening of construction periods, the design structure for Mitsubishi PWR nuclear power plants was thoroughly consolidated with regard to layout and piping design. At the same time, diversified design improvements were made with the excellent domestic technology based on plant designs imported from the U.S.A. An outline of the priority items is introduced in this paper. (author)

Innovations in and by nuclear technology - review and perspectives

International Nuclear Information System (INIS)

Barthelt, K.

1984-01-01

An innovative technology like nuclear technology does not make progress by itself once it has to prove its profitability. It was a long way from technical to economic perfection which took courageous managemental descisions. Since nuclear fission was discovered, its exploitation as an energy source has been perfected. Now it is not only technically safe, reliable and ecological; it has also proved to be economically efficient as compared with the competing primary energies. As with other great innovations, the innovative force of nuclear technology is characterized by two directions: its assimilating capacity and its expanding capacity. Further issues are the so-called technological spin-off of nuclear technology and the fresh impetus nuclear technology gives to other fields. Another aspect beyond technological spin-off affecting all of our society: It was the first large technology requiring risk analyses to be carried out. Discussion broke out in public on the question: ''How safe is nuclear technology''. To sum up, the basic innovation of nuclear technology is now an important economic factor. It came just in time. It is capable of providing relief to the world's energy problems. It is up to us to use it in an intelligent way in the future despite any short-breathed complaints. (orig./HSCH) [de

INTERNATIONAL TECHNOLOGY TRANSFER AND LOCALIZATION: SUCCESS STORIES IN NUCLEAR BRANCH

Directory of Open Access Journals (Sweden)

Yulia V. Chernyakhovskaya

2016-01-01

Full Text Available countries are considering nuclear power industry development [2, p. 3; 3, p. 3; 4]. For newcomer-countries it is of great importance to stimulate the national industry through NPP projects implementation based on technology transfer and localization (TTL. The study and systematization of world experience is useful in purpose to elaborate the national industry development programs. Objectives. The aim of article is to determine success factors of TTL; tasks: 1 to study TTL international experience in the fi eld of nuclear power technologies; 2 on the ground of the world practice to analyze preconditions, contents, stages, arrangement modes, formats and results of TTL. Methods. The following methods are utilized in the study: analysis and synthesis including problem-chronological, cause and eff ect and logical analysis and historical-diachronic method (method of periodization. Results. The following conclusions presented below have been made on the basis of the three cases study related to nuclear industry development using TTL (France, South Korea and China. Conclusions. The TTL success factors includes: Government support that provides long-term governmental development plan of nuclear power and industry for nuclear power based on TTL, and an appropriate international cooperation (under favorable conditions of “NPP buyers market”; Complex approach to implementation of the national TTL program and NPP construction projects: signing of NPP construction contracts with vendors stipulating technology transfer; NPP designing and constructing should be performed jointly with training and transferring of technical documentation and software. Technology transfer cooperation should be implemented through the licenses agreements and setting up joint ventures; Public acceptance and support.

Development of nuclear fuel cycle technology

International Nuclear Information System (INIS)

Kawahara, Akira; Sugimoto, Yoshikazu; Shibata, Satoshi; Ikeda, Takashi; Suzuki, Kazumichi; Miki, Atsushi.

1990-01-01

In order to establish the stable supply of nuclear fuel as an important energy source, Hitachi ltd. has advanced the technical development aiming at the heightening of reliability, the increase of capacity, upgrading and the heightening of performance of the facilities related to nuclear fuel cycle. As for fuel reprocessing, Japan Nuclear Fuel Service Ltd. is promoting the construction of a commercial fuel reprocessing plant which is the first in Japan. The verification of the process performance, the ensuring of high reliability accompanying large capacity and the technical development for recovering effective resources from spent fuel are advanced. Moreover, as for uranium enrichment, Laser Enrichment Technology Research Association was founded mainly by electric power companies, and the development of the next generation enrichment technology using laser is promoted. The development of spent fuel reprocessing technology, the development of the basic technology of atomic process laser enrichment and so on are reported. In addition to the above technologies recently developed by Hitachi Ltd., the technology of reducing harm and solidification of radioactive wastes, the molecular process laser enrichment and others are developed. (K.I.)

Designing Human Technologies

DEFF Research Database (Denmark)

Simonsen, Jesper

and the design process, in ethical and society-related concerns, and in evaluating how designs fulfill needs and solve problems. Designing Human Technologies subscribes to a broad technology concept including information and communication, mobile, environmental/sustainable and energy technologies......Design is increasingly becoming a part of the university curriculum and research agenda. The keynote present and discuss Designing Human Technologies – an initiative aiming at establishing a design oriented main subject area alongside traditional main subject areas such as Natural Science......, the Humanities, and Social Science. The initiative broadens the perspective of IS and recognize reflections on aesthetics, ethics, values, connections to politics, and strategies for enabling a better future as legitimate parts of the research agenda. Designing Human Technologies is a design-oriented Strategic...

Nuclear power technologies. Abstracts of reports

International Nuclear Information System (INIS)

Koltysheva, G.I.; Mukusheva, M.K.; Perepelkin, I.G.

2000-01-01

In May 14-17, 2000, and on the initiative of the Ministry of Science and High Education of the Republic of Kazakstan with cooperation of Department of Energy US, International Seminar on Nuclear Power Technologies was held in Astana, Kazakhstan. More than 70 reports of scientists from different countries (USA, Russia, Japan and Kazakhstan) were presented during the Seminar. Representatives from different international organizations (European Commission Delegation, IAEA), from organizations of Kazakstan, Russia, USA, Japan took part in the Seminar. In all at the Seminar there were more then 100 participants. The Seminar included Plenary Session, two sections: 1) Nuclear Safety and Nuclear Technologies; 2) Material Investigations for Nuclear and Thermonuclear Power; Workshop: Nuclear Facilities Decommissioning and Decontamination; and Posters

U. S. Fuel Cycle Technologies R and D Program for Next Generation Nuclear Materials Management

International Nuclear Information System (INIS)

Miller, M. C.; Vega, D. A.

2013-01-01

The U. S. Department of Energy's Fuel Cycle Technologies R and D program under the Office of Nuclear Energy is working to advance technologies to enhance both the existing and future fuel cycles. One thrust area is in developing enabling technologies for next generation nuclear materials management under the Materials Protection, Accounting and Control Technologies (MPACT) Campaign where advanced instrumentation, analysis and assessment methods, and security approaches are being developed under a framework of Safeguards and Security by Design. An overview of the MPACT campaign's activities and recent accomplishments is presented along with future plans

Spallation-based science and technology and associated nuclear data requirements

International Nuclear Information System (INIS)

Bowman, C.D.; Lisowski, P.W.; Arthur, E.D.

1990-01-01

Rapid advances in accelerator technology in recent years promise average proton beam currents as high as 250 mA with energies greater than one GeV. Such an accelerator could produce very high intensities of neutrons and other nuclear particles thus opening up new areas of science and technology. An example is the efficient burning of transuranic and fission product waste. With such a spallation-burner it appears that high-level waste might be converted to low-level waste on a time scale comparable to the human lifespan at a reasonable additional cost for electric power generation. The emphasis of this paper is on the design of a high power proton target for neutron production, on the nuclear data needed to operate this target safely and effectively, and on data requirements for transmutation. It is suggested that a pilot facility consisting of a 1.6 GeV accelerator and target operating at 25 ma is the next major step in developing this technology. Bursts of protons near the terawatt level might also be generated using such an accelerator with a proton accumulator ring. Research prospects based on such proton bursts are briefly described. The status of established nuclear data needs and of accelerator-based sources for nuclear data measurements is reviewed. (author)

International academic program in technologies of light-water nuclear reactors. Phases of development and implementation

International Nuclear Information System (INIS)

Geraskin, N I; Glebov, V B

2017-01-01

The results of implementation of European educational projects CORONA and CORONA II dedicated to preserving and further developing nuclear knowledge and competencies in the area of technologies of light-water nuclear reactors are analyzed. Present article addresses issues of design and implementation of the program for specialized training in the branch of technologies of light-water nuclear reactors. The systematic approach has been used to construct the program for students of nuclear specialties, which corresponding to IAEA standards and commonly accepted nuclear principles recognized in the European Union. Possibilities of further development of the international cooperation between countries and educational institutions are analyzed. Special attention is paid to e-learning/distance training, nuclear knowledge preservation and interaction with European Nuclear Education Network. (paper)

Advances in nuclear science and technology

CERN Document Server

Henley, Ernest J

1973-01-01

Advances in Nuclear Science and Technology, Volume 7 provides information pertinent to the fundamental aspects of nuclear science and technology. This book discusses the safe and beneficial development of land-based nuclear power plants.Organized into five chapters, this volume begins with an overview of irradiation-induced void swelling in austenitic stainless steels. This text then examines the importance of various transport processes for fission product redistribution, which depends on the diffusion data, the vaporization properties, and the solubility in the fuel matrix. Other chapters co

The impact of safety standards updating for design purposes in nuclear power plants licensing

International Nuclear Information System (INIS)

Alvarenga, Marco Antonio Bayout; Rabello, Sidney Luiz

2009-01-01

The Brazilian experience of nuclear power plants licensing was consolidated by the use of the Brazilian, American, German and IAEA standards. Independently of the set of norms, standards or guides to be used, this set should be in consonance with the state-of-art or the current state of knowledge in science and technology. In the general design criteria of US NRC or German BMI, or in the Brazilian norms (CNEN) or even, in the IAEA standards, this aspect is always emphasized. On the other hand, the international operational experience of nuclear reactors (for example, TMI accident) also contributes to the updating of norms and standards. The use of new technologies (for example, digital technology) impels the norms and standards to adopt new design criteria related to the new technological context. Moreover, we must add the particular vision that each country can have concerning to specific topics in nuclear safety. This work discusses how the norms, standards and guides used in the nuclear licensing are being reviewed to cope with the requirement of the state-of-art. In order to accomplish this aim we took some general design criteria to exemplify how they are fulfilled, mainly those related directly with the protection of the defense-in-depth barriers: primary coolant system, containment vessel and containment systems, including external events and severe accidents. In complement to the deterministic analysis, it is also discussed the design criteria related to the human factors engineering and probabilistic safety analysis, including severe accidents aspects. (author)

Progress report on nuclear science and technology in China (Vol.2). Proceedings of academic annual meeting of China Nuclear Society in 2011, No.7--Nuclear electronics and nuclear detection technology sub-volume

International Nuclear Information System (INIS)

2012-10-01

Progress report on nuclear science and technology in China (Vol. 2) includes 698 articles which are communicated on the second national academic annual meeting of China Nuclear Society. There are 10 books totally. This is the seventh one, the content is about Nuclear electronics and nuclear detection technology

Current status of Chinese nuclear power industry and technology

International Nuclear Information System (INIS)

Kim, Hyun Min; Kim, Min; Jeong, Hee Jong; Hwang, Jeong Ki; Cho, Chung Hee

1996-10-01

China has been carrying out active international cooperation aiming to be a country where is to be an economical super power and an advanced country in nuclear power technology by the year early 2000, and China also has begun to be recognized as the largest potential market for the construction of nuclear power plants(NPPs) expecting to construct more than thirty nuclear power units by the year 2020. China has advanced technology in the basic nuclear science including liquid metal breeder reactor technology, nuclear material, medium and small size power plants, and isotope production technology, and also China has complete nuclear fuel cycle technology. However, China still has low NPP technology. Therefore, it is expected that China may have complementary cooperative relationship with China, it is expected that Korea may have an access to the advanced Chinese nuclear science technology, and may have a good opportunity to explore the Chinese market actively exporting excellent Korean NPP technology, and further may have a good position to the neighboring Asian countries' NPP markets. From this perspective, general Chinese social status, major nuclear R and D activity status, and correct NPP and technology status have been analyzed in this report, and this report is expected to be a useful resource for cooperating with China in future. 10 tabs., 6 figs., 16 refs. (Author)

Briefings on nuclear technology in India

International Nuclear Information System (INIS)

Iyengar, P.K.

2009-01-01

Few scientists one knows of, have gone out of their way to educate the public-especially those involved in making policies at the government level-on what nuclear energy is all about and how it is produced. One might begin at the beginning and ask what the basic principles of scientific research are, how they are developed and what the methodology of converting science into technology is. Equally relevantly, how can one sensitise the administration, not to speak of the average citizen, in supporting science and technology. This work is divided into nine chapters. The first one discusses what science really is. The second introduces the reader to nuclear science and technology. The third progressively deals with Indian effort in developing nuclear science and the astounding amount of organisational effort involved. The fourth refers to nuclear testing, a somewhat controversial subject. The fifth addresses itself to the problem of nuclear non-proliferation, yet another controversial subject, but which Dr Iyengar deals with commendable objectivity. The last three chapters concern administrative reforms

Recent technology for BWR nuclear steam turbine unit

International Nuclear Information System (INIS)

Moriya, Shin-ichi; Masuda, Toyohiko; Kashiwabara, Katsuto; Oshima, Yoshikuni

1990-01-01

As to the ABWR plants which is the third improvement standard boiling water reactor type plants, already the construction of a plant of 1356 MWe class for 50 Hz is planned. Hitachi Ltd. has accumulated the technology for the home manufacture of a whole ABWR plant including a turbine. As the results, the application of a butterfly type combination intermediate valve to No.5 plant in Kashiwazaki Kariwa Nuclear Power Station, Tokyo Electric Power Co., Inc., which began the commercial operation recently and later plants, the application of a moisture separating heater to No.4 plant in Hamaoka Nuclear Power Station, Chubu Electric Power Co., Inc., which is manufactured at present and later plants and so on were carried out. As to the steam turbine facilities for nuclear power generation manufactured by Hitachi Ltd., three turbines of 1100 MWe class for 50 Hz and one turbine for 60 Hz are in operation. As the new technologies for the steam turbines, the development of 52 in long last stage blades, the new design techniques for the rotor system, the moisture separating heater, the butterfly type combination intermediate valve, cross-around pipes and condensate and feedwater system are reported. (K.I.)

Nuclear industry technology boomerang

International Nuclear Information System (INIS)

Scholler, R.W.

1987-01-01

The benefits to the medical, pharmaceutical, semiconductor, computer, video, bioscience, laser, defense, and numerous high-tech industries from nuclear technology development fallout are indeed numerous and increase every day. Now those industries have made further progress and improvements that, in return, benefit the nuclear industry. The clean-air and particle-free devices and enclosures needed for protection and decontamination are excellent examples

Upgrading of seismic design of nuclear power plant building

Energy Technology Data Exchange (ETDEWEB)

Akiyama, Hiroshi [Tokyo Univ. (Japan). Faculty of Engineering; Kitada, Yoshio

1997-03-01

In Japan seismic design methodology of nuclear power plant (NPP) structures has been established as introduced in the previous session. And yet efforts have been continued to date to upgrade the methodology, because of conservative nature given to the methodology in regard to unknown phenomena and technically-limited modeling involved in design analyses. The conservative nature tends to produce excessive safety margins, and inevitably send NPP construction cost up. Moreover, excessive seismic design can increase the burden on normal plant operation, though not necessarily contributing to overall plant safety. Therefore, seismic engineering has put to many tests and simulation analyses in hopes to rationalize seismic design and enhance reliability of seismic safety of NPPs. In this paper, we describe some studies on structural seismic design of NPP underway as part of Japan`s effort to upgrade existing seismic design methodology. Most studies described here are carried out by NUPEC (Nuclear Power Engineering Company) funded by MITI (the Ministry of International Trade and Industry Japan), though, similar studies with the same motive are also carrying out by nuclear industries such as utilities, NPP equipment and system manufacturers and building constructors. This paper consists of three sections, each introducing studies relating to NPP structural seismic design, new siting technology, and upgrading of the methodology of structural design analyses. (J.P.N.)

Upgrading of seismic design of nuclear power plant building

International Nuclear Information System (INIS)

Akiyama, Hiroshi; Kitada, Yoshio.

1997-01-01

In Japan seismic design methodology of nuclear power plant (NPP) structures has been established as introduced in the previous session. And yet efforts have been continued to date to upgrade the methodology, because of conservative nature given to the methodology in regard to unknown phenomena and technically-limited modeling involved in design analyses. The conservative nature tends to produce excessive safety margins, and inevitably send NPP construction cost up. Moreover, excessive seismic design can increase the burden on normal plant operation, though not necessarily contributing to overall plant safety. Therefore, seismic engineering has put to many tests and simulation analyses in hopes to rationalize seismic design and enhance reliability of seismic safety of NPPs. In this paper, we describe some studies on structural seismic design of NPP underway as part of Japan's effort to upgrade existing seismic design methodology. Most studies described here are carried out by NUPEC (Nuclear Power Engineering Company) funded by MITI (the Ministry of International Trade and Industry Japan), though, similar studies with the same motive are also carrying out by nuclear industries such as utilities, NPP equipment and system manufacturers and building constructors. This paper consists of three sections, each introducing studies relating to NPP structural seismic design, new siting technology, and upgrading of the methodology of structural design analyses. (J.P.N.)

Progress report on nuclear science and technology in China (Vol.3). Proceedings of academic annual meeting of China Nuclear Society in 2013, No.7--Nuclear electronics and nuclear detection technology sub-volume

International Nuclear Information System (INIS)

2014-05-01

Progress report on nuclear science and technology in China (Vol. 3) includes 57 articles which are communicated on the third national academic annual meeting of China Nuclear Society. There are 10 books totally. This is the seventh one, the content is about Nuclear electronics and nuclear detection technology sub-volume

Success in nuclear technology transfer: A Canadian perspective

International Nuclear Information System (INIS)

Lawson, D.S.; Stevens, J.E.S.; Boulton, J.

1986-10-01

Technology transfer has played a significant part in the expansion of nuclear power to many countries of the world. Canada's involvement in nuclear technology transfer spans four decades. The experience gained through technology transfer, initially to Canadian industry and then to other countries in association with the construction of CANDU nuclear power plants, forms a basis from which to assess the factors which contribute to successful technology transfer. A strong commitment from all parties, in terms of both financial and human resources, is essential to success. Detailed planning of both the scope and timing of the technology transfer program is also required together with an assessment of the impact of the introduction of nuclear power on other sectors of the economy. (author)

2012 annual meeting on nuclear technology. Workshop on 'Preservation of competence in nuclear technology'

International Nuclear Information System (INIS)

Steinwarz, Wolfgang

2012-01-01

Within the 2-day workshop on 'Preservation of Competence in Nuclear Technology,' 31 young scientists competed for the 'Competence Prize' awarded by Siempelkamp Nukleartechnik for the 14th time. They reported about their papers focusing on nuclear technology, reactor technology, innovative reactor systems, radioactive waste management, radiological protection and energy supply systems. The jury composed of Prof. J. Starflinger (Universitaet Stuttgart, IKE), Prof. M.K. Koch (Ruhr-Universitaet Bochum, LEE), and Dr. W. Steinwarz (Siempelkamp Nukleartechnik) assessed the advance compacts as well as the oral presentations. The winner of the 2012 Competence Prize is Dipl.-Ing.(M.S.) Thomas M. Fesich (University Stuttgart). Dr.-Ing. Oliver Czaikowski (Techn. University Clausthal) and Dipl.-Ing. Mario Kuschewski (Universitaet Stuttgart) won the second and third prizes. (orig.)

Nuclear energy technology transfer: the security barriers

International Nuclear Information System (INIS)

Rinne, R.L.

1975-08-01

The problems presented by security considerations to the transfer of nuclear energy technology are examined. In the case of fusion, the national security barrier associated with the laser and E-beam approaches is discussed; for fission, the international security requirements, due to the possibility of the theft or diversion of special nuclear materials or sabotage of nuclear facilities, are highlighted. The paper outlines the nuclear fuel cycle and terrorist threat, examples of security barriers, and the current approaches to transferring technology. (auth)

Science and technology as strategic way for nuclear activities

International Nuclear Information System (INIS)

Paiano, Silvestre

2000-01-01

The article brings few instructive examples on the interaction between nuclear energy and other areas of science and technology, Microelectronics, computer technology, and new materials are among the many technologies which are crucial for developing nuclear energy technology. On the other way round, nuclear energy presents also a wide range of new demands and opportunities for several areas of science and technology. The problem is that such a relationship is not well understood by the society, and to a large extent it brings about the very process of legitimating the use of nuclear energy (author)

Nuclear science and technology education and training in Indonesia

International Nuclear Information System (INIS)

Karsono

2007-01-01

Deployment of nuclear technology requires adequate nuclear infrastructure which includes governmental infrastructure, science and technology infrastructure, education and training infrastructure, and industrial infrastructure. Governmental infrastructure in nuclear, i.e. BATAN (the National Nuclear Energy Agency) and BAPETEN (the Nuclear Energy Control Agency), need adequate number of qualified manpower with general and specific knowledge of nuclear. Science and technology infrastructure is mainly contained in the R and D institutes, education and training centers, scientific academies and professional associations, and national industry. The effectiveness of this infrastructure mainly depends on the quality of the manpower, in addition to the funding and available facilities. Development of human resource needed for research, development, and utilization of nuclear technology in the country needs special attention. Since the national industry is still in its infant stage, the strategy for HRD (human resource development) in the nuclear field addresses the needs of the following: BATAN for its research and development, promotion, and training; BAPETEN for its regulatory functions and training; users of nuclear technology in industry, medicine, agriculture, research, and other areas; radiation safety officers in organizations or institutions licensed to use radioactive materials; the education sector, especially lecturers and teachers, in tertiary and secondary education. Nuclear science and technology is a multidisciplinary and a highly specialized subject. It includes areas such as nuclear and reactor physics, thermal hydraulics, chemistry, material science, radiation protection, nuclear safety, health science, and radioactive waste management. Therefore, a broad nuclear education is absolutely essential to master the wide areas of science and technology used in the nuclear domain. The universities and other institutions of higher education are the only

EPRI nuclear power plant decommissioning technology program

International Nuclear Information System (INIS)

Kim, Karen S.; Bushart, Sean P.; Naughton, Michael; McGrath, Richard

2011-01-01

The Electric Power Research Institute (EPRI) is a non-profit research organization that supports the energy industry. The Nuclear Power Plant Decommissioning Technology Program conducts research and develops technology for the safe and efficient decommissioning of nuclear power plants. (author)

Innovative waste treatment and conditioning technologies at nuclear power plants

International Nuclear Information System (INIS)

2006-05-01

nuclear power plant, other waste generators, or regulatory bodies. What is absent from the available literature is a publication written for managers, plant designers, and other decision makers which will assist them to synthesize the growing list of available technologies in a way which best meets their local needs. Thus, a need existed to develop a document which provides an overview of the innovative technologies currently employed at or in support of NPP, including the applicable waste streams, benefits and impacts of each technology, current applications within the nuclear community (who is using the technology), and any non-technical innovative approaches. This publication provides that information for key decision makers. The report was prepared by series of consultants and technical meetings during 2004-2006. A list of contributors to review of the material collected and to drafting and revision of the report is provided at the end of this report

Promoting the acceptance of nuclear technology

International Nuclear Information System (INIS)

Rueckl, E.

1998-01-01

Restoring the public acceptance of nuclear technology requires optimized public relations work and an enhanced interaction among the nuclear industry and schools and universities. Thinking in contexts needs to be promoted, also in order to improve knowledge of mass flows. Specific terms often mean different things to experts and to the public. This can be corrected by careful use of language and precision in public relations work. The young generation is more openminded towards technology now than it was in the seventies and eighties. This is a point of departure in winning young people also for nuclear technology. For this to happen, science education in schools needs to be improved and the appropriate courses need to be introduced. (orig.) [de

Application of Recommended Design Practices for Conceptual Nuclear Fusion Space Propulsion Systems

Science.gov (United States)

Williams, Craig H.

2004-01-01

An AIAA Special Project Report was recently produced by AIAA's Nuclear and Future Flight Propulsion Technical Committee and is currently in peer review. The Report provides recommended design practices for conceptual engineering studies of nuclear fusion space propulsion systems. Discussion and recommendations are made on key topics including design reference missions, degree of technological extrapolation and concomitant risk, thoroughness in calculating mass properties (nominal mass properties, weight-growth contingency and propellant margins, and specific impulse), and thoroughness in calculating power generation and usage (power-flow, power contingencies, specific power). The report represents a general consensus of the nuclear fusion space propulsion system conceptual design community and proposes 15 recommendations. This paper expands on the Report by providing specific examples illustrating how to apply each of the recommendations.

Department of Nuclear Equipment '' High Technology Center - HITEC '' - Overview

International Nuclear Information System (INIS)

Krawczyk, P.

2010-01-01

Full text: The Department of Nuclear Equipment specializes in applications of accelerator technologies in medicine and industrial radiography. It combines research and development with manufacturing activities. The year 2009 was an important and busy period for the Department. We expect to observe already its full results in the coming year. In 2009, the Department concentrated on developing technologies, solutions and elements for use in the new generation of medical accelerators. Design, manufacturing and tests of a model of a new accelerating structure were conducted. The overall mechanical and electrical design of the accelerator was reworked and partially tested. Major efforts were devoted to creating an efficient software environment for the accelerators: new concepts for the control system were developed and tested, and a recording and verification system based on the DICOM standard was completed. A new imaging system was designed and manufactured and work on the associated imaging software was initiated. Design work on a multileaf collimator, begun in 2008, was continued. In effect, an operational model of the device was manufactured which allowed a practical verification of the design ideas. A lull scale prototype is scheduled for manufacture in 2010. The 2009 edition of the HITEC School on Medical Accelerators was directed to Medical Technicians. Very positive feedback from the participants proves the correctness of that decision. The year 2009 was also important for the manufacturing capabilities of the Department of Nuclear Equipment: a new Precision Machining Workshop was established and equipped with modern CNC milling machines. Also, the Vacuum Technologies Laboratory significantly extended the range of its machinery. In 2009 HITEC underwent deep organizational changes. The Quality Management System that governs all aspects of the Department's activities was also substantially redesigned. In December 2009, the new System was successfully audited and

Proceedings of 8. national conference on nuclear electronic and nuclear detection technology: Pt.1

International Nuclear Information System (INIS)

1996-01-01

The 8th National Conference on Nuclear Electronics and Nuclear Detection Technology was held during 2-7, 12, 1996 in Zhuhai, Guangdong, China. 184 pieces of papers were collected in the conference proceedings. The contents of the conference proceedings are: nuclear electronics, nuclear detectors, nuclear instruments and its application, nuclear medical electronics, computer applications in nuclear sciences and technology, measurement of nuclear monitoring and nuclear explosion, radiation hardened electronics, liquid scintillation counting techniques and miscellaneous. Reported hereafter is the first part of the proceedings

AP1000, a nuclear central of advanced design; AP1000, una central nuclear de diseno avanzado

Energy Technology Data Exchange (ETDEWEB)

Hernandez M, N.; Viais J, J. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: nhm@nuclear.inin.mx

2005-07-01

The AP1000 is a design of a nuclear reactor of pressurized water (PWR) of 1000 M We with characteristic of safety in a passive way; besides presenting simplifications in the systems of the plant, the construction, the maintenance and the safety, the AP1000 is a design that uses technology endorsed by those but of 30 years of operational experience of the PWR reactors. The program AP1000 of Westinghouse is focused to the implementation of the plant to provide improvements in the economy of the same one and it is a design that is derived directly of the AP600 designs. On September 13, 2004 the US-NRC (for their initials in United States- Nuclear Regulatory Commission) approved the final design of the AP1000, now Westinghouse and the US-NRC are working on the whole in a complete program for the certification. (Author)

Robotics and nuclear power. Report by the Technology Transfer Robotics Task Team

International Nuclear Information System (INIS)

1985-06-01

A task team was formed at the request of the Department of Energy to evaluate and assess technology development needed for advanced robotics in the nuclear industry. The mission of these technologies is to provide the nuclear industry with the support for the application of advanced robotics to reduce nuclear power generating costs and enhance the safety of the personnel in the industry. The investigation included robotic and teleoperated systems. A robotic system is defined as a reprogrammable, multifunctional manipulator designed to move materials, parts, tools, or specialized devices through variable programmed motions for the performance of a variety of tasks. A teleoperated system includes an operator who remotely controls the system by direct viewing or through a vision system

Development of interface technology for nuclear hydrogen production system

International Nuclear Information System (INIS)

Lee, Ki Young; Park, J. K.; Chang, J. H.

2012-06-01

These works focus on the development of attainment indices for nuclear hydrogen key technologies, the analysis of the hydrogen production process and the performance estimation for hydrogen production systems, and the assessment of the nuclear hydrogen production economy. The codes for analyzing the hydrogen production economy are developed for calculating the unit production cost of nuclear hydrogen. We developed basic R and D quality management methodology to meet design technology of VHTR's needs. By putting it in practice, we derived some problems and solutions. We distributed R and D QAP and Q and D QAM to each teams and these are in operation. Computer simulations are performed for estimating the thermal efficiency for the electrodialysis component likely to adapting as one of the hydrogen production system in Korea and EED-SI process known as the key components of the hydrogen production systems. Using the commercial codes, the process diagrams and the spread-sheets were produced for the Bunsen reaction process, Sulphuric Acid dissolution process and HI dissolution process, respectively, which are the key components composing of the SI process

Proceedings of the Nuclear Engineering Science and Technology - NESTeT 2011 Transactions

International Nuclear Information System (INIS)

2011-01-01

This important European Nuclear Society (ENS) conference is dedicated to networking in nuclear education and training across the fields of engineering, science and technology. It is organised as a back-to-back event with the European Nuclear Young Generation Forum (ENYGF) which will attract over 150 Young Professionals from all over Europe. Exchange of information on available expertise, capacity, infrastructure and needs, together with networking and collaboration between all stakeholders involved is crucial for the development of an efficient education and training system that is able to provide adequately skilled workforce for a dynamically evolving sector. NESTet is designed to facilitate an exchange of information, collaboration and the sharing of best practices in nuclear education and training in engineering science and technology. It is an important networking opportunity for better co-ordination and collaboration between different stakeholders. The conference is targeted at all stakeholders responsible for human resources and skills development and stakeholders responsible for the development of education and training programmes in the nuclear sector. (authors)

2005 annual nuclear technology conference

International Nuclear Information System (INIS)

Anon.

2005-01-01

This year's Annual Nuclear Technology Conference of the Deutsches Atomforum and Kerntechnische Gesellschaft was held in Nuremberg on May 10-12, 2005. More than 1 100 participants from eighteen countries make this specialized event one of the largest international conventions in the field of the peaceful uses of nuclear power, whose attendance has steadily increased over the past few years. The first day of the conference was devoted to plenary lectures traditionally dealing mainly with political and economic problems of the use of nuclear power. The partner country of JK 2005 was Switzerland. Traditionally, the program of the three-day conference was organized in the proven format of plenary sessions on the first day, followed by technical sessions, specialized sessions, poster sessions, and special events on the following days. For the third time, the ''Nuclear Campus'' was organized which successfully made the world of nuclear technology transparent to high school and university students in lectures and an exhibition. The meeting was accompanied by a technical exhibition with meeting points of manufacturers, suppliers, and service industries. (orig.)

Nuclear technology in research and everyday life

International Nuclear Information System (INIS)

2015-12-01

The paper.. discusses the impact of nuclear technology in research and everyday life covering the following issues: miniaturization of memory devices, neutron radiography in material science, nuclear reactions in the universe, sterilization of food, medical applies, cosmetics and packaging materials using beta and gamma radiation, neutron imaging for radioactive waste analysis, microbial transformation of uranium (geobacter uraniireducens), nuclear technology knowledge preservation, spacecrafts voyager 1 and 2, future fusion power plants, prompt gamma activation analysis in archeology, radiation protection and radioecology and nuclear medicine (radiotherapy).

Serving human needs. Nuclear technologies in the marketplace

International Nuclear Information System (INIS)

Qian Jihui; Burkart, Werner

2001-01-01

Many peaceful nuclear technologies today stand firmly established. They are being widely applied and accepted around the world in such fields as health care, food production, manufacturing, electricity generation, and environmental protection. Among the IAEA's 132 Member States, interest in constructively applying the tools of nuclear science and technology - especially outside the energy sector - remains high, although priorities, needs, and policies have changed over time. For the IAEA - whose specific mandate is to 'accelerate and enlarge the contribution of atomic energy to peace, health, and prosperity' - the changing and challenging global picture has strengthened efforts to enhance the contribution of nuclear science and technologies in key fields of human development. A multi-faceted programme of technical cooperation serves as the main vehicle for the transfer of nuclear science and technology to developing countries. The programme's emphasis is on supporting projects that respond to the priority needs of each country, produce an economic or social impact, and reflect the distinct advantages of nuclear technology over other approaches

Nuclear Knowledge Preservation Initiative: Strategies, Information Technology Options And The Future

International Nuclear Information System (INIS)

Mundu, M.A

2004-01-01

The launching of National Nuclear Programme and the designation of OAU Ife and Ahmadu Bello University, Zaria as centers of excellence in nuclear research in 1977 marked the beginning of a systematic development of manpower and physical infrastructure for the peaceful application of nuclear science and technology are carried out in the Universities Research Institutes and the Industry, in Health, Hydrology, Agriculture, Petroleum, Mineral Development and Environmental Management. A major challenge arising form these development, is the collection, accumulated over the years. The resolution adopted on nuclear knowledge at the IAEA General Conference in 2002 and 2003 has given us the impetus to reposition the INIS centre toward the establishment of an information resource capable of meeting the needs of our scientists and engineers. A necessary step toward this end is to build a network of Universities and Research Institutes in nuclear science that will be used to pool, analyze and share national nuclear knowledge and experience, address preservation and promotion of knowledge, maintain competence and avoid duplication wherever necessary. This paper discusses the strategies, information technology options, stake holders and their responsibilities and the way forward

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

International Nuclear Information System (INIS)

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

2010-01-01

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

Nuclear power technology requirements for NASA exploration missions

International Nuclear Information System (INIS)

Bloomfield, H.S.

1990-01-01

This paper discusses how future exploration of the Moon and Mars will mandate developments in many areas of technology. In particular, major advances will be required in planet surface power systems and space transportation systems. Critical nuclear technology challenges that can enable strategic self-sufficiency, acceptable operational costs and cost-effective space transportation goals for NASA exploration missions have been identified. Critical technologies for surface power systems include stationary and mobile nuclear reactor and radio-isotope heat sources coupled to static and dynamic power conversion devices. These technologies can provide dramatic reductions in mass leading to operational and transportation cost savings. Critical technologies for space transportation systems include nuclear thermal rocket and nuclear electric propulsion options which present compelling concepts for significantly reducing mass, cost or travel time required for Earth-Mars transport

Proceedings of the 9. National Seminar on Technology and Safety of Nuclear Power Plants and Nuclear Facilities

International Nuclear Information System (INIS)

Antariksawan, Anhar R.; Soetrisnanto, Arnold Y; Aziz, Ferhat; Untoro, Pudji; Su'ud, Zaki; Zarkasi, Amin Santoso; Lasman, As Natio

2003-08-01

The ninth proceedings of seminar safety and technology of nuclear power plant and nuclear facilities held by National Nuclear Energy Agency and PLN-JTK. The aims of seminar is to exchange and disseminate information about Safety and Nuclear Power Plant Technology and Nuclear Facilities consist of Technology High Temperature Reactor and Application for National Development Sustainable and High Technology. This seminar cover all aspects Technology, Power Reactor, Research Reactor High Temperature Reactor and Nuclear Facilities. There are 20 articles have separated index

A study on the international nuclear Co-operation and the nuclear technology self-reliance strategy

International Nuclear Information System (INIS)

Kim, Hwa Sup

1993-02-01

To setup a basement for the national nuclear technology strategy, the reorganization of the world structure and the environmental issues are analyzed. And with regards to the self-reliance of nuclear technology, the method for the settlement of the national nuclear infrastructure and the method to strengthen our role in international nuclear community through the co-operation with IAEA is suggested. Also the status and strategy of major nuclear pushing countries are investigated. And followed by this, national nuclear technology status and strategy are analyzed. (Author)

ISO: international standards development for nuclear technology

International Nuclear Information System (INIS)

Becker, K.

1981-01-01

The importance of internationally recognized standards for nuclear technology and safety is rapidly increasing for technical as well as economical and political reasons such as public acceptance and nuclear technology transfer to developing countries. The need for such standards is also evident because of the large number of nuclear installations sited close to international borders, and the export of nuclear installations from relatively few supplier countries to a large number of user countries. It is the purpose of this report to describe briefly the history, organizational structures and procedures, goals, accomplishments, problems, and future needs of the relevant activities of the International Organization for Standardization (ISO). ISO is composed of the partly governmental, partly non-governmental national standards bodies of 86 countries including China. The work of its Technical Committee (TC) 85 'Nuclear Energy' is mostly concerned with industrial applications, contractual aspects and international communication, for the benefit of both developed and developing countries. It works in close liaison with IAEA, which develops Codes and Guides addressed mainly to the regulatory aspects of nuclear power plants in developing countries. ISO/TC 85 has four sub-committees dealing with: (a) Terminology, Definitions, Units and Symbols (Secretariat USA, four working groups (WGs)); (b) Radiation Protection (Secretariat France, ten WGs); (c) Power Reactor Technology (Secretariat Sweden, nine WGs); (d) Nuclear Fuel Technology (Secretariat F.R. Germany, seven WGs). (author)

Preliminary nuclear power reactor technology qualitative assessment for Malaysia

International Nuclear Information System (INIS)

Shamsul Amri Sulaiman

2011-01-01

Since the worlds first nuclear reactor major breakthrough in December 02, 1942, the nuclear power industry has undergone tremendous development and evolution for more than half a century. After surpassing moratorium of nuclear power plant construction caused by catastrophic accidents at Three-mile island (1979) and Chernobyl (1986), today, nuclear energy is back on the policy agendas of many countries, both developed and developing, signaling nuclear revival or nuclear renaissance. Selection of suitable nuclear power technology has thus been subjected to primary attention. This short paper attempts to draw preliminary technology assessment for the first nuclear power reactor technology for Malaysia. Methodology employed is qualitative analysis collating recent finding of tnb-kepco preliminary feasibility study for nuclear power program in peninsular malaysia and other published presentations and/or papers by multiple experts. The results suggested that pressurized water reactor (PWR) is the prevailing technology in terms of numbers and plant performances, and while the commercialization of generation IV reactors is remote (e.g. Not until 2030), generation III/ III+ NPP models are commercially available on the market today. Five (5) major steps involved in reactor technology selection were introduced with a focus on introducing important aspects of selection criteria. Three (3) categories for the of reactor technology selection were used for the cursory evaluation. The outcome of these analyses shall lead to deeper and full analyses of the recommended reactor technologies for a comprehensive feasibility study in the near future. Recommendations for reactor technology option were also provided for both strategic and technical recommendations. The paper shall also implore the best way to select systematically the first civilian nuclear power reactor. (Author)

Application technology for optical fiber in nuclear facilities

International Nuclear Information System (INIS)

Lee, Jong Min; Kim, Chul Jung; Lee, Yong Bum; Kim, Woong Ki; Yoon, Tae Seob; Sohn, Surg Won; Kim, Chang Hoi; Hwang, Suk Yong; Baik, Sung Hum; Kwon, Seong Ouk

1987-12-01

Lately, the optical fiber increasingly used in such adverse environments as nuclear power plant, radiation facilities because of their endurant properties against heat, radiation, corrosion, etc. Moreover, the transmission of signal through optical fiber does not induce interference from the electromagnetic wave. Basic theory about the optical fiber technology was studied and the developed techniques for nuclear facilities were reviewed. Since the radiations change the characteristics of the optical fiber, the effects of γ-ray irradiation on single mode and multimode optical fiber were examined. The image transmission system through optical fiber bundle was designed, constructed, and tested. Its software system was also updated. It can be used for remote internal inspection in adverse environment. (Author)

Chemistry programmes at a technological and nuclear centre

International Nuclear Information System (INIS)

Servian, J.L.

1984-01-01

The application of chemical principles and techniques have played a major role in the development of nuclear sciences and technology. The discovery of radioactivity, the isolation of radium and polonium, the discovery of artificial radioactivity and nuclear fission and the production of transuranium elements are historical landmarks that show the prominent role performed by chemistry. The purpose of this paper is to summarize the chemistry areas and experimental facilities for programmes of training, research and development, and service that might be designed for implementation at the Centre when appropriate. Though the areas are separately presented for analysis, they are closely related among themselves and also related to other activities of the Centre. (author)

Fuzzy Logic and Intelligent Technologies in Nuclear Science

International Nuclear Information System (INIS)

Da Ruan

1998-01-01

FLINS is the acronym for Fuzzy Logic and Intelligent Technologies in Nuclear Science. The main task for FLINS is to solve intricate problems pertaining to the nuclear environment by using modern technologies as additional tools and to bridge the gap between novel technologies and the industrial nuclear world. In 1997, major efforts went to the specific prototyping of Fuzzy Logic Control of SCK-CEN's BR1 research Reactor. Progress and achievements are reported

Development of Demonstration Facility Design Technology for Advanced Nuclear Fuel Cycle Process

International Nuclear Information System (INIS)

Cho, Il Je; You, G. S.; Choung, W. M.

2010-04-01

The main objective of this R and D is to develop the PRIDE (PyRoprocess Integrated inactive DEmonstration) facility for engineering-scale inactive test using fresh uranium, and to establish the design requirements of the ESPF (Engineering Scale Pyroprocess Facility) for active demonstration of the pyroprocess. Pyroprocess technology, which is applicable to GEN-IV systems as one of the fuel cycle options, is a solution of the spent fuel accumulation problems. PRIDE Facility, pyroprocess mock-up facility, is the first facility that is operated in inert atmosphere in the country. By using the facility, the functional requirements and validity of pyroprocess technology and facility related to the advanced fuel cycle can be verified with a low cost. Then, PRIDE will contribute to evaluate the technology viability, proliferation resistance and possibility of commercialization of the pyroprocess technology. The PRIDE evaluation data, such as performance evaluation data of equipment and operation experiences, will be directly utilized for the design of ESPF

Towards a nuclear energy technology roadmap. A new service to the nuclear community

International Nuclear Information System (INIS)

Van Den Durpel, Luc; Thomas, Chris Creighton

2005-01-01

The role of nuclear energy in a future sustainable energy mix has been the subject of debates over the past few years. The future for nuclear energy will not only depend on this energy market development and the socio-political environment, but also on the innovation potential of the nuclear community to cope with the ever shorter business cycles in the energy market and the inherently longer term horizon needed in developing nuclear energy at its potential. Today's nuclear R and D community is in a transition phase, i.e. from former 'national' R and D-organisational structure to a truly international research area based on partnerships between organisations and companies creating networks-of-excellence. Several studies in the recent past have indicated the need for a shared vision in guiding this process. Identification of shared R and D-programmes, mergers and acquisitions of organizations and companies, knowledge gap analysis and the strategic mapping for each organization or company active in this nuclear R and D community. Technology Roadmapping is the appropriate tool to respond to these needs. Several stand-alone nuclear roadmap activities have been undertaken but lacked the possibility to analyse and make use of the synergies and interactions inherent to this technology development. The development has started of a master nuclear roadmap portal covering all the roadmap and technology foresight information in one so-called master nuclear roadmap. This master nuclear roadmap is implemented in an electronic online format allowing easy access, easy updating and lots of functionalities which may not be offered by traditional snap-shot roadmap reports. The paper will bring an overview on the role that technology roadmapping is playing in various industry sectors and the added value it may bring in the nuclear technology sector on a organizational as well as technology sector level. The paper will highlight the current status of this new initiative. (author)

Safety of nuclear power plants: Design. Safety requirements

International Nuclear Information System (INIS)

2000-01-01

The present publication supersedes the Code on the Safety of Nuclear Power Plants: Design (Safety Series No. 50-C-D (Rev. 1), issued in 1988). It takes account of developments relating to the safety of nuclear power plants since the Code on Design was last revised. These developments include the issuing of the Safety Fundamentals publication, The Safety of Nuclear Installations, and the present revision of various safety standards and other publications relating to safety. Requirements for nuclear safety are intended to ensure adequate protection of site personnel, the public and the environment from the effects of ionizing radiation arising from nuclear power plants. It is recognized that technology and scientific knowledge advance, and nuclear safety and what is considered adequate protection are not static entities. Safety requirements change with these developments and this publication reflects the present consensus. This Safety Requirements publication takes account of the developments in safety requirements by, for example, including the consideration of severe accidents in the design process. Other topics that have been given more detailed attention include management of safety, design management, plant ageing and wearing out effects, computer based safety systems, external and internal hazards, human factors, feedback of operational experience, and safety assessment and verification. This publication establishes safety requirements that define the elements necessary to ensure nuclear safety. These requirements are applicable to safety functions and the associated structures, systems and components, as well as to procedures important to safety in nuclear power plants. It is expected that this publication will be used primarily for land based stationary nuclear power plants with water cooled reactors designed for electricity generation or for other heat production applications (such as district heating or desalination). It is recognized that in the case of

Safety of nuclear power plants: Design. Safety requirements

International Nuclear Information System (INIS)

2004-01-01

The present publication supersedes the Code on the Safety of Nuclear Power Plants: Design (Safety Series No. 50-C-D (Rev. 1), issued in 1988). It takes account of developments relating to the safety of nuclear power plants since the Code on Design was last revised. These developments include the issuing of the Safety Fundamentals publication, The Safety of Nuclear Installations, and the present revision of various safety standards and other publications relating to safety. Requirements for nuclear safety are intended to ensure adequate protection of site personnel, the public and the environment from the effects of ionizing radiation arising from nuclear power plants. It is recognized that technology and scientific knowledge advance, and nuclear safety and what is considered adequate protection are not static entities. Safety requirements change with these developments and this publication reflects the present consensus. This Safety Requirements publication takes account of the developments in safety requirements by, for example, including the consideration of severe accidents in the design process. Other topics that have been given more detailed attention include management of safety, design management, plant ageing and wearing out effects, computer based safety systems, external and internal hazards, human factors, feedback of operational experience, and safety assessment and verification. This publication establishes safety requirements that define the elements necessary to ensure nuclear safety. These requirements are applicable to safety functions and the associated structures, systems and components, as well as to procedures important to safety in nuclear power plants. It is expected that this publication will be used primarily for land based stationary nuclear power plants with water cooled reactors designed for electricity generation or for other heat production applications (such as district heating or desalination). It is recognized that in the case of

A line technology of subterranean mining by means of nuclear explosions

International Nuclear Information System (INIS)

Gushchin, V.V.; Vasin, K.D.; Nifontov, B.I.; Odrov, Yu.L.; Myasnikov, K.V.; Kol'tsov, V.M.; Kornev, G.N.; Degtyarev, V.A.

1976-01-01

The basic principles of a line technology of extracting firm ores, including break-up of ore by means of subterranean nuclear explosions, the removal of ore from sorting blocks by means of vibrator feeders and transporting it to intermediate levels via a new type of belt conveyor on mobile supports are considered. A method of crushing ore by nuclear explosions on reflecting surfaces is proposed to obtain a more uniform fragmentation of ore, increase the output of fragmented ore per unit capacity, and to preserve mining output. The basic principles of designing a system of mining based on a line technology are formulated and one variant of such a system is presented

Nuclear power strategy: requirements for technology