Prospects for nuclear safety research

Energy Technology Data Exchange (ETDEWEB)

Beckjord, E.S.

1995-04-01

This document is the text of a paper presented by Eric S. Beckjord (Director, Nuclear Regulatory Research/NRC) at the 22nd Water Reactor Safety Meeting in Bethesda, MD in October 1994. The following topics are briefly reviewed: (1) Reactor vessel research, (2) Probabilistic risk assessment, (3) Direct containment heating, (4) Advanced LWR research, (5) Nuclear energy prospects in the US, and (6) Future nuclear safety research. Subtopics within the last category include economics, waste disposal, and health and safety.

Progress of nuclear safety research. 2001

Energy Technology Data Exchange (ETDEWEB)

Anoda, Yoshinari; Sasajima, Hideo; Nishiyama, Yutaka (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [and others

2001-10-01

JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy or the Safety Research Annual Plan issued by the Japanese government. The safety research at JAERI concerns the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety. This report summarizes the nuclear safety research activities of JAERI from April 1999 through March 2001. (author)

Advanced maintenance research programs

International Nuclear Information System (INIS)

Marston, T.U.; Gelhaus, F.; Burke, R.

1985-01-01

The purpose of this paper is to provide the reader with an idea of the advanced maintenance research program at the Electric Power Research Institute (EPRI). A brief description of the maintenance-related activities is provided as a foundation for the advanced maintenance research projects. The projects can be divided into maintenance planning, preventive maintenance program development and implementation, predictive (or conditional) maintenance, and innovative maintenance techniques. The projects include hardware and software development, human factors considerations, and technology promotion and implementation. The advanced concepts include: the incorporation of artificial intelligence into outage planning; turbine and pump maintenance; rotating equipment monitoring and diagnostics with the aid of expert systems; and the development of mobile robots for nuclear power plant maintenance

Evaluation and development of advanced nuclear materials: IAEA activities

International Nuclear Information System (INIS)

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

2011-01-01

Economical, environmental and non-proliferation issues associated with sustainable development of nuclear power bring about a need for optimization of fuel cycles and implementation of advanced nuclear systems. While a number of physical and design concepts are available for innovative reactors, the absence of reliable materials able to sustain new challenging irradiation conditions represents the real bottle-neck for practical implementation of these promising ideas. Materials performance and integrity are key issues for the safety and competitiveness of future nuclear installations being developed for sustainable nuclear energy production incorporating fuel recycling and waste transmutation systems. These systems will feature high thermal operational efficiency, improved utilization of resources (both fissile and fertile materials) and reduced production of nuclear waste. They will require development, qualification and deployment of new and advanced fuel and structural materials with improved mechanical and chemical properties combined with high radiation and corrosion resistance. The extensive, diverse, and expensive efforts toward the development of these materials can be more effectively organized within international collaborative programmes with wide participation of research, design and engineering communities. IAEA carries out a number of international projects supporting interested Member States with the use of available IAEA program implementation tools (Coordinated Research Projects, Technical Meetings, Expert Reviews, etc). The presentation summarizes the activities targeting material developments for advanced nuclear systems, with particular emphasis on fast reactors, which are the focal topics of IAEA Coordinated Research Projects 'Accelerator Simulation and Theoretical Modelling of Radiation Effects' (on-going), 'Benchmarking of Structural Materials Pre-Selected for Advanced Nuclear Reactors', 'Examination of advanced fast reactor fuel and core

Workshop of Advanced Science Research Center, JAERI. Nuclear physics and nuclear chemistry of superheavy elements

International Nuclear Information System (INIS)

Nishio, Katsuhisa; Nishinaka, Ichiro; Ikezoe, Hiroshi; Nagame, Yuichiro

2004-03-01

A liquid drop model predicts that the fission barrier of a nucleus whose atomic number (Z) is larger than 106 disappears, so that such heavier nuclei as Z > 106 cannot exist. The shell effect, however, drastically changes structure of the fission barrier and stabilizes nucleus against fission, predicting the presence of super heavy element (SHE, Z=114-126) with measurable half-life. In the SHE region, a wave function of outermost electron of an atom, which controls chemical properties of an elements, is disturbed or changed by relativistic effects compared to the one from the non-relativistic model. This suggests that the SHEs have different chemical properties from those of lighter elements belonging to the same family. The chemistry of SHEs requires event by event analysis to reveal their chemical properties, thus is called 'atom-at-a-time chemistry'. Japan Atomic Energy Research Institute (JAERI) has been investigating fusion mechanism between heavy nuclei to find out favorable reactions to produce SHE by using JAERI-tandem and booster accelerator. In the JAERI-tandem facility, isotopes of Rf and Db are produced by using actinide targets such as 248 Cm in order to investigate their chemical properties. The present workshop was held in Advanced Science Research Center of JAERI at February 27-28 (2003) in order to discuss current status and future plans for the heavy element research. The workshop also included topics of the radioactive nuclear beam project forwarded by the JAERI-KEK cooperation and the nuclear transmutation facility of J-PARC. Also included is the nuclear fission process as a decay characteristic of heavy elements. There were sixty participants in the workshop including graduate and undergraduate eleven students. We had guests from Germany and Hungary. Through the workshop, we had a common knowledge that researches on SHE in Japan should fill an important role in the world. (author)

Proceedings of the NATO Advanced Research Workshop on Countering Nuclear and Radiological Terrorism

International Nuclear Information System (INIS)

Apikyan, S.; Diamond, D.

2006-01-01

The objective of this workshop was to identify connections between technology needs and the underlying science and technology, and to establish research strategies that will advanced our ability to counter this form of terrorism. The objectives were met by bringing together international experts familiar with the relevant technologies and policies at a four-day workshop that was held at the Regional Advanced Science and Technology Center (ASTEC), Yerevan, Armenia during October 2005. The many topics covered included: radiation detector development, risk assessment and decision making, decontamination techniques, structural materials resistance to conventional explosives, vulnerability and physical protection of nuclear facilities, security of radiation sources, response to radiological dispersion devices, relevant international and national laws, and non-proliferation

Global development of advanced nuclear power plants, and related IAEA activities

International Nuclear Information System (INIS)

2006-09-01

Renewed interest in the potential of nuclear energy to contribute to a sustainable worldwide energy mix is underlining the IAEA's statutory role in fostering the peaceful uses of nuclear energy, in particular the need for effective exchanges of information and collaborative research and technology development among Member States on advanced nuclear power technologies deployable in the near term as well as in the longer term. For applications in the medium to longer term, with rising expectations for the role of nuclear energy in the future, technological innovation has become a strong focus of nuclear power technology developments by many Member States. To meet Member States' needs, the IAEA conducts activities to foster information exchange and collaborative research and development in the area of advanced nuclear reactor technologies. These activities include coordination of collaborative research, organization of international information exchange, and analyses of globally available technical data and results, with a focus on reducing nuclear power plant capital costs and construction periods while further improving performance, safety and proliferation resistance. In other activities, evolutionary and innovative advances are catalyzed for all reactor lines such as advanced water cooled reactors, high temperature gas cooled reactors, liquid metal cooled reactors and accelerator driven systems, including small and medium sized reactors. In addition, there are activities related to other applications of nuclear energy such as seawater desalination, hydrogen production, and other process heat applications. This brochure summarizes the worldwide status and the activities related to advanced nuclear power technology development and related IAEA activities. It includes a list of the collaborative research and development projects conducted by the IAEA, as well as of the status reports and other publications produced

Proceedings of GLOBAL 2007 conference on advanced nuclear fuel cycles and systems

International Nuclear Information System (INIS)

2007-01-01

In keeping with the 12-year history of this conference, GLOBAL 2007 focuses on future nuclear energy systems and fuel cycles. With the increasing public acceptance and political endorsement of nuclear energy, it is a pivotal time for nuclear energy research. Significant advances have been made in development of advanced nuclear fuels and materials, reactor designs, partitioning, transmutation and reprocessing technologies, and waste management strategies. In concert with the technological advances, it is more important than ever to develop sensible nuclear proliferation policies, to promote sustainability, and to continue to increase international collaboration. To further these aims, GLOBAL 2007 highlights recent developments in the following areas: advanced integrated fuel cycle concepts, spent nuclear fuel reprocessing, advanced reprocessing technology, advanced fuels and materials, advanced waste management technology, novel concepts for waste disposal and repository development, advanced reactors, partitioning and transmutation, developments in nuclear non-proliferation technology, policy, and implementation, sustainability and expanded global utilization of nuclear energy, and international collaboration on nuclear energy

Progress of nuclear safety research-2004

International Nuclear Information System (INIS)

Anoda, Yoshinari; Ebine, Noriya; Chuto, Toshinori; Sato, Satoshi; Ishikawa, Jun; Yamamoto, Toshihiro; Munakata, Masahiro; Asakura, Toshihide; Yamaguchi, Tetsuji; Kida, Takashi; Matsui, Hiroki; Haneishi, Akihiro; Araya, Fumimasa

2005-03-01

JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Annual Plan for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI are the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI has taken a responsible role by providing technical experts and investigation for assistance to the government or local public body. This report summarizes the nuclear safety research activities of JAERI from April 2002 through March 2004 and utilized facilities. (author)

Trends in the design of advanced nuclear reactors

International Nuclear Information System (INIS)

Poong-Eil Juhn; Kupitz, Juergen

1996-01-01

Nuclear energy is an essentially unlimited energy source with the potential to provide energy in the form of electricity, district heat and process heat environmentally acceptable conditions. However, this potential will be realized only if nuclear power plants can meet the challenges of national safety requirements, economic competitiveness and public acceptance. Worldwide, a tremendous amount of experience has been accumulated during the development, licensing, construction and operation of nuclear power plants. This experience forms a sound basis for further improvements. Nuclear programmes in the IAEA Member States are addressing the development of advanced reactors, which are intended to have better economics, higher reliability and improved safety. The IAEA, as a global international governmental organization dealing with nuclear power, promotes international information exchange and international co-operation between all countries with their own advanced power programmes and offers assistance to countries with an interest in exploratory or research programmes. The paper gives an overview of global trends in the design of advanced nuclear reactors for electricity generation and heat production along with the role of IAEA. (author)

Advanced LWR Nuclear Fuel Cladding Development

International Nuclear Information System (INIS)

Bragg-Sitton, S.; Griffith, G.

2012-01-01

The Advanced Light Water Reactor (LWR) Nuclear Fuel Development Research and Development (R and D) Pathway encompasses strategic research focused on improving reactor core economics and safety margins through the development of an advanced fuel cladding system. To achieve significant operating improvements while remaining within safety boundaries, significant steps beyond incremental improvements in the current generation of nuclear fuel are required. Fundamental enhancements are required in the areas of nuclear fuel composition, cladding integrity, and fuel/cladding interaction to allow improved fuel economy via power uprates and increased fuel burn-up allowance while potentially improving safety margin through the adoption of an 'accident tolerant' fuel system that would offer improved coping time under accident scenarios. In a staged development approach, the LWRS program will engage stakeholders throughout the development process to ensure commercial viability of the investigated technologies. Applying minimum performance criteria, several of the top-ranked materials and fabrication concepts will undergo a rigorous series of mechanical, thermal and chemical characterization tests to better define their properties and operating potential in a relatively low-cost, nonnuclear test series. A reduced number of options will be recommended for test rodlet fabrication and in-pile nuclear testing under steady-state, transient and accident conditions. (author)

Advance in study of intelligent diagnostic method for nuclear power plant

International Nuclear Information System (INIS)

Zhou Gang; Yang Li

2008-01-01

The advance of research on the application of three types of intelligent diagnostic approach based on neural network (ANN), fuzzy logic and expert system to the operation status monitoring and fault diagnosis of nuclear power plant (NPP) was reviewed. The research status and characters on status monitoring and fault diagnosis approaches based on neural network, fuzzy logic and expert system for nuclear power plant were analyzed. The development trend of applied research on intelligent diagnostic approaches for nuclear power plant was explored. The analysis results show that the research achievements on intelligent diagnostic approaches based on fuzzy logic and expert system for nuclear power plant are not much relatively. The research of intelligent diagnostic approaches for nuclear power plant concentrate on the aspect of operation status monitoring and fault diagnosis based on neural networks for nuclear power plant. The advancing tendency of intelligent diagnostic approaches for nuclear power plant is the combination of various intelligent diagnostic approaches, the combination of neural network diagnostic approaches and other diagnostic approaches as well as multiple neural network diagnostic approaches. (authors)

NATO Advanced Research Workshop “Nuclear Power and Energy Security”

CERN Document Server

Apikyan, Samuel A; Nuclear Power and Energy Security

2010-01-01

World energy consumption has grown dramatically over the past few decades. This growth in energy demand will be driven by large increases in both economic growth and world population coupled with rising living standards in rapidly growing countries. The last years, we routinely hear about a "renaissance" of nuclear energy. The recognition that nuclear power is vital to global energy security in the 21st century has been growing for some time. "The more we look to the future, the more we can expect countries to be considering the potential benefits that expanding nuclear power has to offer for the global environment and for economic growth," IAEA Director General Mohamed ElBaradei said in advance of a gathering of 500 nuclear power experts assembled in Moscow for the "International Conference on Fifty Years of Nuclear Power - the Next Fifty Years". But such a renaissance is not a single-valued and sure thing. Legitimate four unresolved questions remain about high relative costs; perceived adverse safety, envir...

Technology readiness levels for advanced nuclear fuels and materials development

Energy Technology Data Exchange (ETDEWEB)

Carmack, W.J., E-mail: jon.carmack@inl.gov [Idaho National Laboratory, Idaho Falls, ID (United States); Braase, L.A.; Wigeland, R.A. [Idaho National Laboratory, Idaho Falls, ID (United States); Todosow, M. [Brookhaven National Laboratory, Upton, NY (United States)

2017-03-15

Highlights: • Definition of nuclear fuels system technology readiness level. • Identification of evaluation criteria for nuclear fuel system TRLs. • Application of TRLs to fuel systems. - Abstract: The Technology Readiness process quantitatively assesses the maturity of a given technology. The National Aeronautics and Space Administration (NASA) pioneered the process in the 1980s to inform the development and deployment of new systems for space applications. The process was subsequently adopted by the Department of Defense (DoD) to develop and deploy new technology and systems for defense applications. It was also adopted by the Department of Energy (DOE) to evaluate the maturity of new technologies in major construction projects. Advanced nuclear fuels and materials development is needed to improve the performance and safety of current and advanced reactors, and ultimately close the nuclear fuel cycle. Because deployment of new nuclear fuel forms requires a lengthy and expensive research, development, and demonstration program, applying the assessment process to advanced fuel development is useful as a management, communication, and tracking tool. This article provides definition of technology readiness levels (TRLs) for nuclear fuel technology as well as selected examples regarding the methods by which TRLs are currently used to assess the maturity of nuclear fuels and materials under development in the DOE Fuel Cycle Research and Development (FCRD) Program within the Advanced Fuels Campaign (AFC).

CESAR robotics and intelligent systems research for nuclear environments

International Nuclear Information System (INIS)

Mann, R.C.

1992-01-01

The Center for Engineering Systems Advanced Research (CESAR) at the Oak Ridge National Laboratory (ORNL) encompasses expertise and facilities to perform basic and applied research in robotics and intelligent systems in order to address a broad spectrum of problems related to nuclear and other environments. For nuclear environments, research focus is derived from applications in advanced nuclear power stations, and in environmental restoration and waste management. Several programs at CESAR emphasize the cross-cutting technology issues, and are executed in appropriate cooperation with projects that address specific problem areas. Although the main thrust of the CESAR long-term research is on developing highly automated systems that can cooperate and function reliably in complex environments, the development of advanced human-machine interfaces represents a significant part of our research. 11 refs

Advanced Measuring (Instrumentation Methods for Nuclear Installations: A Review

Directory of Open Access Journals (Sweden)

Wang Qiu-kuan

2012-01-01

Full Text Available The nuclear technology has been widely used in the world. The research of measurement in nuclear installations involves many aspects, such as nuclear reactors, nuclear fuel cycle, safety and security, nuclear accident, after action, analysis, and environmental applications. In last decades, many advanced measuring devices and techniques have been widely applied in nuclear installations. This paper mainly introduces the development of the measuring (instrumentation methods for nuclear installations and the applications of these instruments and methods.

Aims of advanced photon science research

International Nuclear Information System (INIS)

Kimura, Toyoaki

2004-01-01

The Advanced Photon Research Center (APRC) of Japan Atomic Energy Research Institute is pursing the research and development of advanced photon sources such as a compact, ultra-short, high intensity laser, x-ray laser, and a superconducting linac-based free electron laser (FEL) and their applications. These compact and high-intensity lasers have various capabilities of producing radiations with distinguishing characteristics of ultra-short pulse, high coherence, etc. Hence, they can provide novel means of research in the field of nuclear energy applications and industrial and medical technologies. It is important for us to promote these researches on these high-intensity laser applications comprehensively and effectively under the collaborations with nationwide universities and industry. From this point of view it is expected that the APRC plays a role as a COE for these researches. Through these research activities for development of high-intensity lasers and their applications, we will develop ''photon science and technology'' as a leading key technology in the 21st century and contribute the development of science and technology including nuclear energy technology and production of new industries. (author)

Nuclear Capacity Building through Research Reactors

International Nuclear Information System (INIS)

2017-01-01

Four Instruments: •The IAEA has recently developed a specific scheme of services for Nuclear Capacity Building in support of the Member States cooperating research reactors (RR) willing to use RRs as a primary facility to develop nuclear competences as a supporting step to embark into a national nuclear programme. •The scheme is composed of four complementary instruments, each of them being targeted to specific objective and audience: Distance Training: Internet Reactor Laboratory (IRL); Basic Training: Regional Research Reactor Schools; Intermediate Training: East European Research Reactor Initiative (EERRI); Group Fellowship Course Advanced Training: International Centres based on Research Reactors (ICERR)

Progress of nuclear safety research - 2005

International Nuclear Information System (INIS)

Anoda, Yoshinari; Amaya, Masaki; Saito, Junichi; Sato, Atsushi; Sono, Hiroki; Tamaki, Hitoshi; Tonoike, Kotaro; Nemoto, Yoshiyuki; Motoki, Yasuo; Moriyama, Kiyofumi; Yamaguchi, Tetsuji; Araya, Fumimasa

2006-03-01

The Japan Atomic Energy Research Institute (JAERI), one of the predecessors of the Japan Atomic Energy Agency (JAEA), had conducted nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Five-Years Program for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI were the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI had conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI had taken a responsible role by providing experts in assistance to conducting accident investigations or emergency responses by the government or local government. These nuclear safety research and technical assistance to the government have been taken over as an important role by JAEA. This report summarizes the nuclear safety research activities of JAERI from April 2003 through September 2005 and utilized facilities. (author)

Utilization of MCNP code in the research and design for China advanced research reactor

International Nuclear Information System (INIS)

Shen Feng

2006-01-01

MCNP, which is the internationalized neutronics code, is used for nuclear research and design in China Advanced Research Reactor (CARR). MCNP is an important neutronics code in the research and design for CARR since many calculation tasks could be undertaken by it. Many nuclear parameters on reactor core, the design and optimization research for many reactor utilizations, much verification for other nuclear calculation code and so on are conducted with help of MCNP. (author)

Research and development of advanced robots for nuclear power plants

International Nuclear Information System (INIS)

Tsukune, Hideo; Hirukawa, Hirohisa; Kitagaki, Kosei; Liu, Yunhui; Onda, Hiromu; Nakamura, Akira

1994-01-01

Social and economic demands have been pressing for automation of inspection tasks, maintenance and repair jobs of nuclear power plants, which are carried out by human workers under circumstances with high radiation level. Since the plants are not always designed for introduction of automatic machinery, sophisticated robots shall play a crucial role to free workers from hostile environments. We have been studying intelligent robot systems and regarded nuclear industries as one of the important application fields where we can validate the feasibility of the methods and systems we have developed. In this paper we firstly discuss on the tasks required in nuclear power plants. Secondly we introduce current status of R and D on special purpose robots, versatile robots and intelligent robots for automatizing the tasks. Then we focus our discussions on three major functions in realizing robotized assembly tasks under such unstructured environments as in nuclear power plants; planning, vision and manipulation. Finally we depict an image of a prototype robot system for nuclear power plants based on the advanced functions. (author) 64 refs

Progress of nuclear safety research. 2002

Energy Technology Data Exchange (ETDEWEB)

Anoda, Yoshinari; Kudo, Tamotsu; Tobita, Tohru (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] (and others)

2002-11-01

JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Annual Plan for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI are the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI has taken a responsible role by providing technical experts and investigation for assistance to the government or local public body. This report summarizes the nuclear safety research activities of JAERI from April 2000 through April 2002 and utilized facilities. This report also summarizes the examination of the ruptured pipe performed for assistance to the Nuclear and Industrial Safety Agency (NISA) for investigation of the accident at the Hamaoka Nuclear Power Station Unit-1 on November, 2001. (author)

Research advancements and applications of carboranes in nuclear medicinal chemistry

International Nuclear Information System (INIS)

Chen Wen; Wei Hongyuan; Luo Shunzhong

2011-01-01

Because of their uniquely high thermal and chemical stabilities, carboranes have become a subject of study with high interest in the chemistry of supra molecules, catalysts and radiopharmaceuticals. In recent years, the role of carboranes in nuclear medicinal chemistry has been diversified, from the traditional use in boron neutron capture therapy (BNCT), to the clinical applications in molecular radio imaging and therapy. This paper provides an overview of the synthesis and characterization of carboranes and their applications in nuclear medicinal chemistry, with highlights of recent key advancements in the re- search areas of BNCT and radio imaging. (authors)

Frontier of Advanced Accelerator Applications and Medical Treatments Using Nuclear Techniques. Abstract

International Nuclear Information System (INIS)

2015-01-01

To address the challenges of research-based practice, developing advanced accelerator applications, and medical treatments using nuclear tecniqoes, researchers from Rajamakala University of Technology Lanna, Office of Atoms for Peace, and Chiang Mai University have joined in hosting this conference. Nuclear medicine, amedical specialty, diagnoses and treats diseases in a safe and painless way. Nuclear techniques can determine medical information that may otherwise be unavailable, require surgery, or necessitate more expensive and invasive diagnostic tests. Advance in nuclear techniques also offer the potential to detect abnormalities at earlier stages, leasding to earlier treatment and a more successful prognosis.

Advanced LWR Nuclear Fuel Cladding System Development Trade-Off Study

Energy Technology Data Exchange (ETDEWEB)

Kristine Barrett; Shannon Bragg-Sitton

2012-09-01

The Advanced Light Water Reactor (LWR) Nuclear Fuel Development Research and Development (R&D) Pathway encompasses strategic research focused on improving reactor core economics and safety margins through the development of an advanced fuel cladding system. To achieve significant operating improvements while remaining within safety boundaries, significant steps beyond incremental improvements in the current generation of nuclear fuel are required. Fundamental improvements are required in the areas of nuclear fuel composition, cladding integrity, and the fuel/cladding interaction to allow power uprates and increased fuel burn-up allowance while potentially improving safety margin through the adoption of an “accident tolerant” fuel system that would offer improved coping time under accident scenarios. With a development time of about 20 – 25 years, advanced fuel designs must be started today and proven in current reactors if future reactor designs are to be able to use them with confidence.

Indian advanced nuclear reactors

International Nuclear Information System (INIS)

Saha, D.; Sinha, R.K.

2005-01-01

For sustainable development of nuclear energy, a number of important issues like safety, waste management, economics etc. are to be addressed. To do this, a number of advanced reactor designs as well as fuel cycle technologies are being pursued worldwide. The advanced reactors being developed in India are the AHWR and the CHTR. Both the reactors use thorium based fuel and have many passive features. This paper describes the Indian advanced reactors and gives a brief account of the international initiatives for the sustainable development of nuclear energy. (author)

Nuclear safety research at the European Commission's Joint Research Centre

International Nuclear Information System (INIS)

Toerroenen, K.

2003-01-01

Nuclear power plants currently generate some 35 % of electricity used in the European Union and applicant countries. Nuclear safety will therefore remain a priority for the EU, particularly in view of enlargement, the need to monitor ageing nuclear installations and the licencing of advanced new reactor systems. The European Commission's Joint Research Centre (JRC), with its long involvement and recognised competence in nuclear safety related activities, provides direct support to the European Commission services responsible for nuclear safety and civil protection. (author)

Advanced Detectors for Nuclear, High Energy and Astroparticle Physics

CERN Document Server

Das, Supriya; Ghosh, Sanjay

2018-01-01

The book presents high-quality papers presented at a national conference on ‘Advanced Detectors for Nuclear, High Energy and Astroparticle Physics’. The conference was organized to commemorate 100 years of Bose Institute. The book is based on the theme of the conference and provides a clear picture of basics and advancement of detectors for nuclear physics, high-energy physics and astroparticle physics together. The topics covered in the book include detectors for accelerator-based high energy physics; detectors for non-accelerator particle physics; nuclear physics detectors; detection techniques in astroparticle physics and dark matter; and applications and simulations. The book will be a good reference for researchers and industrial personnel working in the area of nuclear and astroparticle physics.

Research method of nuclear patent information

International Nuclear Information System (INIS)

Mo Dan; Gao An'na; Sun Chenglin; Wang Lei; You Xinfeng

2010-01-01

When faced with a huge amount of nuclear patent information, the key to effective research include: (1) Choose convenient way to search, quick access to nuclear technology related patents; (2) To overcome the language barrier, analysis the technical content of patent information; (3) Organize the publication date of retrieved patent documents, analysis the status and trends of nuclear technology development; (4) Research the patented technology of main applicants; (5) Always pay attention to the legal status of patent information, free use the invalid patents, at the same time avoid the patent infringement. Summary, patent information is important to obtain the latest technical information source, and the research work of patent information is a comprehensive understanding and mastery way for advanced nuclear technology. (authors)

Progress of nuclear safety research. 2003

International Nuclear Information System (INIS)

Anoda, Yoshinari; Amagai, Masaki; Tobita, Tohru

2004-03-01

JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Annual Plan for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI are the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI has taken a responsible role by providing technical experts and investigation for assistance to the government or local public body. This report summarizes the nuclear safety research activities of JAERI from April 2001 through March 2003 and utilized facilities. This report also summarizes the examination of the ruptured pipe performed for assistance to the Nuclear and Industrial Safety Agency (NISA) for investigation of the accident at the Hamaoka Nuclear Power Station Unit-1 on November, 2001, and the integrity evaluation of cracked core shroud of BWRs of the Tokyo Electric Power Company performed for assistance to the Nuclear Safety Commission in reviewing the evaluation reports by the licensees. (author)

Recent Advances in Ocean Nuclear Power Plants

Directory of Open Access Journals (Sweden)

Kang-Heon Lee

2015-10-01

Full Text Available In this paper, recent advances in Ocean Nuclear Power Plants (ONPPs are reviewed, including their general arrangement, design parameters, and safety features. The development of ONPP concepts have continued due to initiatives taking place in France, Russia, South Korea, and the United States. Russia’s first floating nuclear power stations utilizing the PWR technology (KLT-40S and the spar-type offshore floating nuclear power plant designed by a research group in United States are considered herein. The APR1400 and SMART mounted Gravity Based Structure (GBS-type ONPPs proposed by a research group in South Korea are also considered. In addition, a submerged-type ONPP designed by DCNS of France is taken into account. Last, issues and challenges related to ONPPs are discussed and summarized.

Supercomputer applications in nuclear research

International Nuclear Information System (INIS)

Ishiguro, Misako

1992-01-01

The utilization of supercomputers in Japan Atomic Energy Research Institute is mainly reported. The fields of atomic energy research which use supercomputers frequently and the contents of their computation are outlined. What is vectorizing is simply explained, and nuclear fusion, nuclear reactor physics, the hydrothermal safety of nuclear reactors, the parallel property that the atomic energy computations of fluids and others have, the algorithm for vector treatment and the effect of speed increase by vectorizing are discussed. At present Japan Atomic Energy Research Institute uses two systems of FACOM VP 2600/10 and three systems of M-780. The contents of computation changed from criticality computation around 1970, through the analysis of LOCA after the TMI accident, to nuclear fusion research, the design of new type reactors and reactor safety assessment at present. Also the method of using computers advanced from batch processing to time sharing processing, from one-dimensional to three dimensional computation, from steady, linear to unsteady nonlinear computation, from experimental analysis to numerical simulation and so on. (K.I.)

Terms for describing new, advanced nuclear power plants

International Nuclear Information System (INIS)

1997-04-01

The IAEA's Division of Nuclear Power and the Fuel Cycle (then the Division of Nuclear Power) took an initiative in this field some years ago when work was initiated in the area of ''safety related terms'' by its International Working Group on Advanced Technologies for Water Cooled Reactors. This activity drew on advice from reactor design organizations, research institutes and government organizations, and aimed at helping eliminate confusion and misuse of safety related terms in widespread use, clarifying technical thinking regarding these terms, and improving nuclear power acceptability by providing precisely described technical meanings to them. After discussion also in the International Working Groups for Gas Cooled Reactors and Fast Reactors, the work resulted in the publication in September 1991 of IAEA-TECDOC-626, entitled ''Safety Related Terms for Advanced Nuclear Plants'', which has become a widely used publication. The present TECDOC has been prepared using the same approach to obtain advice from involved parties. Drafts of this report have been reviewed by the International Working Groups on Water Cooled Reactors, Fast Reactors and Gas Cooled Reactors, as well as by the IAEA's International Fusion Research Council (IFRC). The comments and suggestions received have been evaluated and utilized for producing the present TECDOC. 3 figs

Joint nuclear safety research projects between the US and Russian Federation International Nuclear Safety Centers

International Nuclear Information System (INIS)

Bougaenko, S.E.; Kraev, A.E.; Hill, D.L.; Braun, J.C.; Klickman, A.E.

1998-01-01

The Russian Federation Ministry for Atomic Energy (MINATOM) and the US Department of Energy (USDOE) formed international Nuclear Safety Centers in October 1995 and July 1996, respectively, to collaborate on nuclear safety research. Since January 1997, the two centers have initiated the following nine joint research projects: (1) INSC web servers and databases; (2) Material properties measurement and assessment; (3) Coupled codes: Neutronic, thermal-hydraulic, mechanical and other; (4) Severe accident management for Soviet-designed reactors; (5) Transient management and advanced control; (6) Survey of relevant nuclear safety research facilities in the Russian Federation; (8) Advanced structural analysis; and (9) Development of a nuclear safety research and development plan for MINATOM. The joint projects were selected on the basis of recommendations from two groups of experts convened by NEA and from evaluations of safety impact, cost, and deployment potential. The paper summarizes the projects, including the long-term goals, the implementing strategy and some recent accomplishments for each project

Nuclear imaging: Advances and trends

International Nuclear Information System (INIS)

Herk, G. van

1986-01-01

In this article, nuclear imaging instruments that are likely to be of interest to the nuclear medicine community of developing countries are emphasized. The advances, trends, developments, and future directions in the field of nuclear imaging are mentioned

The Advanced Test Reactor National Scientific User Facility Advancing Nuclear Technology

International Nuclear Information System (INIS)

Allen, T.R.; Benson, J.B.; Foster, J.A.; Marshall, F.M.; Meyer, M.K.; Thelen, M.C.

2009-01-01

To help ensure the long-term viability of nuclear energy through a robust and sustained research and development effort, the U.S. Department of Energy (DOE) designated the Advanced Test Reactor and associated post-irradiation examination facilities a National Scientific User Facility (ATR NSUF), allowing broader access to nuclear energy researchers. The mission of the ATR NSUF is to provide access to world-class nuclear research facilities, thereby facilitating the advancement of nuclear science and technology. The ATR NSUF seeks to create an engaged academic and industrial user community that routinely conducts reactor-based research. Cost free access to the ATR and PIE facilities is granted based on technical merit to U.S. university-led experiment teams conducting non-proprietary research. Proposals are selected via independent technical peer review and relevance to DOE mission. Extensive publication of research results is expected as a condition for access. During FY 2008, the first full year of ATR NSUF operation, five university-led experiments were awarded access to the ATR and associated post-irradiation examination facilities. The ATR NSUF has awarded four new experiments in early FY 2009, and anticipates awarding additional experiments in the fall of 2009 as the results of the second 2009 proposal call. As the ATR NSUF program mature over the next two years, the capability to perform irradiation research of increasing complexity will become available. These capabilities include instrumented irradiation experiments and post-irradiation examinations on materials previously irradiated in U.S. reactor material test programs. The ATR critical facility will also be made available to researchers. An important component of the ATR NSUF an education program focused on the reactor-based tools available for resolving nuclear science and technology issues. The ATR NSUF provides education programs including a summer short course, internships, faculty-student team

Robot vision for nuclear advanced robot

International Nuclear Information System (INIS)

Nakayama, Ryoichi; Okano, Hideharu; Kuno, Yoshinori; Miyazawa, Tatsuo; Shimada, Hideo; Okada, Satoshi; Kawamura, Astuo

1991-01-01

This paper describes Robot Vision and Operation System for Nuclear Advanced Robot. This Robot Vision consists of robot position detection, obstacle detection and object recognition. With these vision techniques, a mobile robot can make a path and move autonomously along the planned path. The authors implemented the above robot vision system on the 'Advanced Robot for Nuclear Power Plant' and tested in an environment mocked up as nuclear power plant facilities. Since the operation system for this robot consists of operator's console and a large stereo monitor, this system can be easily operated by one person. Experimental tests were made using the Advanced Robot (nuclear robot). Results indicate that the proposed operation system is very useful, and can be operate by only person. (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)

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

Non-proliferation and advances in nuclear science

International Nuclear Information System (INIS)

Iyengar, P.K.

1995-01-01

So far, the non-proliferation treaty (NPT) has concentrated on safeguard regimes based on technologies relating to the production of uranium and plutonium in nuclear reactors, and on their potential diversion for use in nuclear weapons. As nuclear science advances, however, nuclear technology both peaceful and for weapons will change, and for the NPT to remain relevant, it must reflect these changes. At this juncture, when the NPT is coming up for review in a year's time, it is important for physicists to take a fresh look at recent advances in nuclear science, and inform the policy-makers and the public at large about their potential for impacting nuclear technology in the future. In this article a few such advances are highlighted and their implications for the NPT are considered. (author). 4 refs

The advanced fuel cycle initiative: the future path for advanced spent fuel treatment and transmutation research in the United States

International Nuclear Information System (INIS)

Herczeg, J.W.

2003-01-01

The U. S. Department of Energy (DOE) has invested over USD 100 million in transmutation research and development over the past three years. The programme has evolved from an accelerator based transmutation programme to a multi-tier reactor and accelerator based programme. These changes have resulted in a significant re-focus of the research and development programme as well as a name change to reflect the new direction. The Advanced Accelerator Application (AAA) programme is now renamed the Advanced Fuel Cycle Initiative (AFCI). Research completed by the AAA programme in Fiscal Year 2002 points to a multi-phased AFCI Programme consisting of two elements that would be conducted in parallel as part of an integrated research effort: an intermediate-term technology element (AFCI Series One), which emphasises advanced technical enhancements to the current commercial nuclear power infrastructure; and a long term technology element (AFCI Series Two), which will require the introduction of next-generation nuclear energy systems to reduce the toxicity of nuclear waste. (author)

Selected advances in materials research

International Nuclear Information System (INIS)

Cunningham, J.E.

1979-01-01

Several findings emanating from materials research that should have a beneficial impact on technological advancement in the future are described. The report deals with the GRAPHNOL, a new class of high-temperature brazing alloy for joining refractory components, gel-sphere-pac process for manufacture of nuclear fuel, and noble-metal fuel cladding for service in radioisotope thermoelectric generators designed to provide auxiliary power aboard spacecraft for planetary exploration

Handbook of advanced nuclear hydrogen safety. 1st edition

International Nuclear Information System (INIS)

Hino, Ryutaro; Takegami, Hiroaki; Ogawa, Toru

2017-03-01

In the aftermath of the Fukushima nuclear accident, safety measures against hydrogen in severe accident has been recognized as a serious technical problem in Japan. Therefore, efforts have begun to form a common knowledge base between nuclear engineers and experts on combustion and explosion, and to secure and improve future nuclear energy safety. As one of such activities, we have prepared the 'Handbook of Advanced Nuclear Hydrogen Safety'. A handbook committee consisting of Japanese experts in the fields of nuclear and combustion-explosion in universities, nuclear companies, electric companies and research institutes was established in 2012. The objective and consents of the handbook were determined, and the outline of the contents was decided. The concepts of the handbook are as follows: to show advanced nuclear hydrogen safety technologies that nuclear engineers should understand, to show hydrogen safety points to make combustion-explosion experts cooperate with nuclear engineers, to expand information on water radiolysis considering the situation from just after the Fukushima accidents and to the waste management necessary for decommissioning after the accident etc. Many experts have participated to manuscript preparation, which was the first step of forming a hydrogen community across the boundaries of fields. The hydrogen community is expected to grow along with its improvement to the knowledge base on nuclear hydrogen safety. (author)

U.S. Department of Energy & Nuclear Regulatory Commission Advanced Fuel Cycle Research & Development Seminar Series FY 2007 & 2008

Energy Technology Data Exchange (ETDEWEB)

Grandy, Christopher [Argonne National Lab. (ANL), Argonne, IL (United States)

2008-08-01

In fiscal year 2007, the Advanced Burner Reactor project initiated an educational seminar series for the Department of Energy (DOE) and Nuclear Regulatory Commission (NRC) personnel on various aspects of fast reactor fuel cycle closure technologies. This important work was initiated to inform DOE and NRC personnel on initial details of sodium-cooled fast reactor, separations, waste form, and safeguard technologies being considered for the Advanced Fuel Cycle Research and Development program, and to learn the important lesson from the licensing process for the Clinch River Breeder Reactor Plant that educating the NRC staff early in the regulatory process is very important and critical to a project success.

The advanced test reactor national scientific user facility advancing nuclear technology

International Nuclear Information System (INIS)

Allen, T.R.; Thelen, M.C.; Meyer, M.K.; Marshall, F.M.; Foster, J.; Benson, J.B.

2009-01-01

To help ensure the long-term viability of nuclear energy through a robust and sustained research and development effort, the U.S. Department of Energy (DOE) designated the Advanced Test Reactor and associated post-irradiation examination facilities a National Scientific User Facility (ATR NSUF), allowing broader access to nuclear energy researchers. The mission of the ATR NSUF is to provide access to world-class nuclear research facilities, thereby facilitating the advancement of nuclear science and technology. The ATR NSUF seeks to create an engaged academic and industrial user community that routinely conducts reactor-based research. Cost free access to the ATR and PIE facilities is granted based on technical merit to U.S. university-led experiment teams conducting non-proprietary research. Proposals are selected via independent technical peer review and relevance to DOE mission. Extensive publication of research results is expected as a condition for access. During FY 2008, the first full year of ATR NSUF operation, five university-led experiments were awarded access to the ATR and associated post-irradiation examination facilities. The ATR NSUF has awarded four new experiments in early FY 2009, and anticipates awarding additional experiments in the fall of 2009 as the results of the second 2009 proposal call. As the ATR NSUF program mature over the next two years, the capability to perform irradiation research of increasing complexity will become available. These capabilities include instrumented irradiation experiments and post-irradiation examinations on materials previously irradiated in U.S. reactor material test programs. The ATR critical facility will also be made available to researchers. An important component of the ATR NSUF an education program focused on the reactor-based tools available for resolving nuclear science and technology issues. The ATR NSUF provides education programs including a summer short course, internships, faculty-student team

Advanced nuclear systems. Review study

International Nuclear Information System (INIS)

Liebert, Wolfgang; Glaser, Alexander; Pistner, Christoph; Baehr, Roland; Hahn, Lothar

1999-04-01

The task of this review study is to from provide an overview of the developments in the field of the various advanced nuclear systems, and to create the basis for more comprehensive studies of technology assessment. In an overview the concepts for advanced nuclear systems pursued worldwide are subdivided into eight subgroups. A coarse examination raster (set pattern) is developed to enable a detailed examination of the selected systems. In addition to a focus on enhanced safety features, further aspects are also taken into consideration, like the lowering of the proliferation risk, the enhancement of the economic competitiveness of the facilities and new usage possibilities (for instance concerning the relaxation of the waste disposal problem or the usage of alternative fuels to uranium). The question about the expected time span for realization and the discussion about the obstacles on the way to a commercially usable reactor also play a substantial role as well as disposal requirements as far as they can be presently recognized. In the central chapter of this study, the documentation of the representatively selected concepts is evaluated as well as existing technology assessment studies and expert opinions. In a few cases where this appears to be necessary, according technical literature, further policy advisory reports, expert statements as well as other relevant sources are taken into account. Contradictions, different assessments and dissents in the literature as well as a few unsettled questions are thus indicated. The potential of advanced nuclear systems with respect to economical and societal as well as environmental objectives cannot exclusively be measured by the corresponding intrinsic or in comparison remarkable technical improvements. The acceptability of novel or improved systems in nuclear technology will have to be judged by their convincing solutions for the crucial questions of safety, nuclear waste and risk of proliferation of nuclear weapons

Nuclear safety research collaborations between the U.S. and Russian Federation International Nuclear Safety Centers

International Nuclear Information System (INIS)

Hill, D. J.; Braun, J. C.; Klickman, A. E.; Bougaenko, S. E.; Kabonov, L. P.; Kraev, A. G.

2000-01-01

The Russian Federation Ministry for Atomic Energy (MINATOM) and the US Department of Energy (USDOE) have formed International Nuclear Safety Centers to collaborate on nuclear safety research. USDOE established the US Center (ISINSC) at Argonne National Laboratory (ANL) in October 1995. MINATOM established the Russian Center (RINSC) at the Research and Development Institute of Power Engineering (RDIPE) in Moscow in July 1996. In April 1998 the Russian center became a semi-independent, autonomous organization under MINATOM. The goals of the center are to: Cooperate in the development of technologies associated with nuclear safety in nuclear power engineering; Be international centers for the collection of information important for safety and technical improvements in nuclear power engineering; and Maintain a base for fundamental knowledge needed to design nuclear reactors. The strategic approach is being used to accomplish these goals is for the two centers to work together to use the resources and the talents of the scientists associated with the US Center and the Russian Center to do collaborative research to improve the safety of Russian-designed nuclear reactors. The two centers started conducting joint research and development projects in January 1997. Since that time the following ten joint projects have been initiated: INSC databases--web server and computing center; Coupled codes--Neutronic and thermal-hydraulic; Severe accident management for Soviet-designed reactors; Transient management and advanced control; Survey of relevant nuclear safety research facilities in the Russian Federation; Computer code validation for transient analysis of VVER and RBMK reactors; Advanced structural analysis; Development of a nuclear safety research and development plan for MINATOM; Properties and applications of heavy liquid metal coolants; and Material properties measurement and assessment. Currently, there is activity in eight of these projects. Details on each of these

Proceedings of the Twenty-First Water Reactor Safety Information Meeting: Volume 1, Plenary session; Advanced reactor research; advanced control system technology; advanced instrumentation and control hardware; human factors research; probabilistic risk assessment topics; thermal hydraulics; thermal hydraulic research for advanced passive LWRs

International Nuclear Information System (INIS)

Monteleone, S.

1994-04-01

This three-volume report contains 90 papers out of the 102 that were presented at the Twenty-First Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 25--27, 1993. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Germany, Japan, Russia, Switzerland, Taiwan, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Individual papers have been cataloged separately. This document, Volume 1 covers the following topics: Advanced Reactor Research; Advanced Instrumentation and Control Hardware; Advanced Control System Technology; Human Factors Research; Probabilistic Risk Assessment Topics; Thermal Hydraulics; and Thermal Hydraulic Research for Advanced Passive Light Water Reactors

Proceedings of the Twenty-First Water Reactor Safety Information Meeting: Volume 1, Plenary session; Advanced reactor research; advanced control system technology; advanced instrumentation and control hardware; human factors research; probabilistic risk assessment topics; thermal hydraulics; thermal hydraulic research for advanced passive LWRs

Energy Technology Data Exchange (ETDEWEB)

Monteleone, S. [Brookhaven National Lab., Upton, NY (United States)] [comp.

1994-04-01

This three-volume report contains 90 papers out of the 102 that were presented at the Twenty-First Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 25--27, 1993. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Germany, Japan, Russia, Switzerland, Taiwan, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Individual papers have been cataloged separately. This document, Volume 1 covers the following topics: Advanced Reactor Research; Advanced Instrumentation and Control Hardware; Advanced Control System Technology; Human Factors Research; Probabilistic Risk Assessment Topics; Thermal Hydraulics; and Thermal Hydraulic Research for Advanced Passive Light Water Reactors.

A modeling and control approach to advanced nuclear power plants with gas turbines

International Nuclear Information System (INIS)

Ablay, Günyaz

2013-01-01

Highlights: • Load frequency control strategies in nuclear plants are researched. • Nuclear reactor-centered control system may not be suitable for load control. • Local unit controllers improve stability and overall time constant. • Coolant loops in nuclear plants should be controlled locally. - Abstract: Advanced nuclear power plants are currently being proposed with a number of various designs. However, there is a lack of modeling and control strategies to deal with load following operations. This research investigates a possible modeling approach and load following control strategy for gas turbine nuclear power plants in order to provide an assessment way to the concept designs. A load frequency control strategy and average temperature control mechanism are studied to get load following nuclear power plants. The suitability of the control strategies and concept designs are assessed through linear stability analysis methods. Numerical results are presented on an advanced molten salt reactor concept as an example nuclear power plant system to demonstrate the validity and effectiveness of the proposed modeling and load following control strategies

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

Advances in nuclear science and technology

CERN Document Server

Greebler, Paul

1966-01-01

Advances in Nuclear Science and Technology, Volume 3 provides an authoritative, complete, coherent, and critical review of the nuclear industry. This book presents the advances in the atomic energy field.Organized into six chapters, this volume begins with an overview of the use of pulsed neutron sources for the determination of the thermalization and diffusion properties of moderating as well as multiplying media. This text then examines the effect of nuclear radiation on electronic circuitry and its components. Other chapters consider radiation effects in various inorganic solids, with empha

Outline of research proposals selected in the Nuclear Energy Research Initiative (NERI) program

International Nuclear Information System (INIS)

Iwamura, Takamichi; Okubo, Tsutomu; Usui, Shuji

1999-08-01

The U.S. Department of Energy (DOE) created a new R and D program called Nuclear Energy Research Initiative (NERI)' in FY 1999 with the appropriation of $19 million. The major objectives of the NERI program is to preserve the nuclear science and engineering infrastructure in the U.S. and to maintain a competitive position in the global nuclear market in the 21st century. In may, 1999, the DOE selected 45 research proposals for the first year of the NERI program. The proposals are classified into the following five R and D areas: Proliferation Resistant Reactors and/or Fuel Cycles, New Reactor Designs, Advanced Nuclear Fuel, New Technology for Management of Nuclear Waste, Fundamental Nuclear Science. Since the NERI is a very epoch-making and strategic nuclear research program sponsored by the U.S. government, the trend of the NERI is considered to affect the future R and D programs in Japanese nuclear industries and research institutes including JAERI. The present report summarizes the analyzed results of the selected 45 research proposals. Staffs comments are made on each proposal in connection with the R and D activities in JAERI. (author)

Open-Source Integrated Design-Analysis Environment For Nuclear Energy Advanced Modeling & Simulation Final Scientific/Technical Report

Energy Technology Data Exchange (ETDEWEB)

O' Leary, Patrick [Kitware, Inc., Clifton Park, NY (United States)

2017-01-30

The framework created through the Open-Source Integrated Design-Analysis Environment (IDAE) for Nuclear Energy Advanced Modeling & Simulation grant has simplify and democratize advanced modeling and simulation in the nuclear energy industry that works on a range of nuclear engineering applications. It leverages millions of investment dollars from the Department of Energy's Office of Nuclear Energy for modeling and simulation of light water reactors and the Office of Nuclear Energy's research and development. The IDEA framework enhanced Kitware’s Computational Model Builder (CMB) while leveraging existing open-source toolkits and creating a graphical end-to-end umbrella guiding end-users and developers through the nuclear energy advanced modeling and simulation lifecycle. In addition, the work deliver strategic advancements in meshing and visualization for ensembles.

Advanced Safeguards Technology Road-map for the Global Nuclear Energy Partnership

International Nuclear Information System (INIS)

Miller, M.C.; Tobin, S.; Smith, L.E.; Ehinger, M.; Dougan, A.; Cipiti, B.; Bakel, A.; Bean, R.

2008-01-01

Strengthening the nonproliferation regime, including advanced safeguards, is a cornerstone of the Global Nuclear Energy Partnership (GNEP). To meet these challenges, the Safeguards Campaign was formed, whose mission is to provide research and technology development for the foundation of next generation safeguards systems for implementation in U.S. GNEP facilities. The Safeguards Campaign works closely with the Nuclear Nonproliferation and International Security department (NA-24) of NNSA (National Nuclear Safety Administration) to ensure that technology developed for domestic safeguards applications are optimum with respect to international safeguards use. A major milestone of the program this year has been the development of the advanced safeguards technology road-map. This paper will broadly describe the road-map, which provides a path to next generation safeguards systems including advanced instrumentation; process monitoring; data integration, protection, and analysis; and system level evaluation and knowledge extraction for real time applications. (authors)

Bolivia. The new nuclear research center in El Alto

International Nuclear Information System (INIS)

Nogarin, Mauro

2016-01-01

Research reactors in Latin America have become a priority in public policy in the last decade. Bolivia wants to become the 8th country to implement peaceful nuclear technology in this area with the new Center for Research and Development in the Nuclear Technology. The Center will be the most advanced in Latin America. It will provide for a wide use of radiation technologies in agriculture, medicine, and industry. After several negotiations Bolivia and the Russian Federation signed the Intergovernmental Agreement on cooperation in the peaceful use of atomic energy and the construction of the Nuclear Research and Technology Center.

Bolivia. The new nuclear research center in El Alto

Energy Technology Data Exchange (ETDEWEB)

Nogarin, Mauro

2016-05-15

Research reactors in Latin America have become a priority in public policy in the last decade. Bolivia wants to become the 8th country to implement peaceful nuclear technology in this area with the new Center for Research and Development in the Nuclear Technology. The Center will be the most advanced in Latin America. It will provide for a wide use of radiation technologies in agriculture, medicine, and industry. After several negotiations Bolivia and the Russian Federation signed the Intergovernmental Agreement on cooperation in the peaceful use of atomic energy and the construction of the Nuclear Research and Technology Center.

Radiation and physical protection challenges at advanced nuclear fuel cycle facilities

International Nuclear Information System (INIS)

Pickett, Susan E.

2008-01-01

detection through research and technology development, as well as regulation and education. Based on the review, this paper outlines key challenges and opportunities for radiation protection and detection technology development, and concludes with a proposal for international cooperation on radiation protection for advanced nuclear power generation facilities.(author)

Studies on environment safety and application of advanced reactor for inland nuclear power plants

International Nuclear Information System (INIS)

Wei, L.; Jie, L.

2014-01-01

To study environment safety assessment of inland nuclear power plants (NPPs), the impact of environment safety under the normal operation was researched and the environment risk of serious accidents was analyzed. Moreover, the requirements and relevant provisions of site selection between international nuclear power plant and China's are comparatively studied. The conclusion was that the environment safety assessment of inland and coastal nuclear power plant have no essential difference; the advanced reactor can meet with high criteria of environment safety of inland nuclear power plants. In this way, China is safe and feasible to develop inland nuclear power plant. China's inland nuclear power plants will be as big market for advanced reactor. (author)

Research on the improvement of nuclear safety -Thermal hydraulic tests for reactor safety system-

Energy Technology Data Exchange (ETDEWEB)

Jung, Moon Kee; Park, Choon Kyung; Yang, Sun Kyoo; Chun, Se Yung; Song, Chul Hwa; Jun, Hyung Kil; Jung, Heung Joon; Won, Soon Yun; Cho, Yung Roh; Min, Kyung Hoh; Jung, Jang Hwan; Jang, Suk Kyoo; Kim, Bok Deuk; Kim, Wooi Kyung; Huh, Jin; Kim, Sook Kwan; Moon, Sang Kee; Lee, Sang Il [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1995-06-01

The present research aims at the development of the thermal hydraulic verification test technology for the safety system of the conventional and advanced nuclear power plant and the development of the advanced thermal hydraulic measuring techniques. In this research, test facilities simulating the primary coolant system and safety system are being constructed for the design verification tests of the existing and advanced nuclear power plant. 97 figs, 14 tabs, 65 refs. (Author).

Plasma physics and nuclear fusion research

CERN Document Server

Gill, Richard D

1981-01-01

Plasma Physics and Nuclear Fusion Research covers the theoretical and experimental aspects of plasma physics and nuclear fusion. The book starts by providing an overview and survey of plasma physics; the theory of the electrodynamics of deformable media and magnetohydrodynamics; and the particle orbit theory. The text also describes the plasma waves; the kinetic theory; the transport theory; and the MHD stability theory. Advanced theories such as microinstabilities, plasma turbulence, anomalous transport theory, and nonlinear laser plasma interaction theory are also considered. The book furthe

Nuclear science and engineering education at a university research reactor

International Nuclear Information System (INIS)

Loveland, W.

1990-01-01

The research and teaching operations of the Nuclear Chemistry Division of the Dept. of Chemistry and the Dept. of Nuclear Engineering are housed at the Oregon State University Radiation Center. This facility which includes a 1.1 MW TRIGA reactor was used for 53 classes from a number of different academic departments last year. About one-half of these classes used the reactor and ∼25% of the reactor's 45 hour week was devoted to teaching. Descriptions will be given of reactor-oriented instructional programs in nuclear engineering, radiation health and nuclear chemistry. In nuclear chemistry, classes in (a) nuclear chemistry for nuclear engineers, (b) radiotracer methods, (c) elementary and advanced activation analysis, and (d) advanced nuclear instrumentation will be described in detail. The use of the facility to promote general nuclear literacy among college students, high school and grade school students and the general population will also be covered

Dossier: management of nuclear wastes. Research, results

International Nuclear Information System (INIS)

Anon.

2001-01-01

The researches carried out since many years on nuclear wastes have led to two main ways of management: the long-term conditioning of radio-elements and their advanced separation. The French atomic energy commission (CEA) has chosen to take up also the transmutation challenge, a way to transform long-living radioactive wastes into short-living radioactive wastes or stable compounds. The transmutation programs are based both on simulation and experiments with a huge international collaboration. This dossier presents in a digest way the research activity carried out on nuclear wastes processing and management at the CEA. (J.S.)

Summary report from 1. research coordination meeting on nuclear data libraries for advance systems - fusion devices (FENDL - 3)

International Nuclear Information System (INIS)

Trkov, A.; Forrest, R.; Mengoni, A.

2009-03-01

The first Research Co-ordination Meeting of the Nuclear Data Libraries for Advance Systems - Fusion Devices (FENDL - 3) was held at the IAEA Headquarters in Vienna from 2 to 5 December 2008. A summary of the meeting is given in this report along with discussions which took place. An important outcome of the meeting was the agreement to create a new FENDL-3.0 Starter Library. Finally, a list of task assignments was prepared together with the plan for future CRP activities. (author)

Nuclear research centres in the 21st century: An AECL perspective

International Nuclear Information System (INIS)

Fehrenbach, P.J.

2001-01-01

The nuclear energy programme of Canada started at Chalk River Laboratories with the setting up of Zero Energy Experimental Site in 1945. One of the early research reactors of Canada, the National Research Universal (NRU) continues to provide 70% of the world requirement of isotopes for medical and industrial applications. A CANDU prototype (208 MW(e)) came on line in 1967 and based on this concept, Canada has a large nuclear power programme. The role of nuclear research centres has evolved with time starting with strategic research in the initial phases through to implementation of technology, building and supporting industry, and carrying out advanced technology development. Most of these centres have important assets in terms of licensed sites, trained personnel, research reactors, shielded facilities and expertise for handling large quantities of radioactivity and high tech laboratories for advanced R and D. These centres would, therefore, continue to play an important role in emission free and economic energy generation, nuclear medicine, food irradiation and industrial applications. Nuclear research centres in different countries are at various stages of development and have many unique features. However, there are generic issues and much will be gained by developing a shared vision for the future and implementing programmes in a collaborative manner. (author)

Status of advanced nuclear reactor development in Korea

International Nuclear Information System (INIS)

Kim, H.R.; Kim, K.K.; Kim, Y.W.; Joo, H.K.

2014-01-01

The Korean nuclear industry is facing new challenges to solve the spent fuel storage problem and meet the needs to diversify the application areas of nuclear energy. In order to provide solutions to these challenges, the Korea Atomic Energy Research Institute (KAERI) has been developing advanced nuclear reactors including a Sodium-cooled Fast Reactor, Very High Temperature Gas cooled Reactor (VHTR), and System-integrated Modular Advanced Reactor (SMART) with substantially improved safety, economics, and environment-friendly features. A fast reactor system is one of the most promising options for a reduction of radioactive wastes. The long-term plan for Advanced SFR development in conjunction with the pyro-process was authorized by the Korean Atomic Energy Commission in 2008. The development milestone includes specific design approval of a prototype SFR by 2020, and the construction of a prototype SFR by 2028. KAERI has been carrying out the preliminary design of a 150MWe SFR prototype plant system since 2012. The development of advanced SFR technologies and the basic key technologies necessary for the prototype SFR are also being carried out. By virtue of high-temperature heat, a VHTR has diverse applications including hydrogen production. KAERI launched a nuclear hydrogen project using a VHTR in 2006, which focused on four basic technologies: the development of design tools, very high-temperature experimental technology, TRISO fuel fabrication, and Sulfur-iodine thermo-chemical hydrogen production technology. The technology development project will be continued until 2017. A conceptual reactor design study was started in 2012 as collaboration between industry and government to enhance the early-launching of the nuclear hydrogen development and demonstration (NHDD) project. The goal of the NHDD project is to design and build a nuclear hydrogen demonstration system by 2030. KAERI has developed SMART which is a small-sized advanced integral reactor with a rated

Specific features of occupational medicine in nuclear research and industry

International Nuclear Information System (INIS)

Giraud, J.M.; Quesne, B.

2003-01-01

Measures to prevent the exposure of personnel to ionising radiation were taken as soon as the first nuclear laboratories were set up. This branch of occupational preventive medicine has since kept pace with advances in research and in the industrial applications of nuclear energy. (authors)

Champion comparison of prestigious nuclear research institutes by thirty-year research papers written in nuclear advanced countries

International Nuclear Information System (INIS)

Yanagisawa, Kazuaki

2010-08-01

A champion of research paper at JAERI and those of foreign prestigious nuclear research institutes (5 from the U.S., 3 from the France and 2 from the Germany) was studied taking the timeframe as long as 30 years (1978-2007) Tools for this bibliometric study were INIS, ECD, WOS and SCOPUS. The former two were general database collected all papers related to nuclear, while the latter two were specified database collected research papers submitted to journals for natural, social sciences and human learning. (1) INIS for the world-wide general tool focused on nuclear judged that JAERI (32,859 papers) was the champion and ORNL (32,395 papers) was the second position. (2) ECD for the US-oriented energy database judged that the ranking was of the order of ORNL(36,608 papers), ANL(26,530) and SNL(24,687). (3) The trend observed in the WOS for the US-oriented database roughly coincided with that of ECD, where ORNL(34,331 papers) was the champion, where JAERI was the 7th position. (4) SCOPUS, basically originated from the Europe judged that that ORNL (32,728 papers) was the champion, where JAERI (16,860) was the 7th position. (5) Different characteristics exhibited by individual databases can sometimes generate conflicting bibliometric results. This was true among INIS, ECD, WOS and SCOPUS when looking at trends between 5-year periods. It implies that results from analytical tools used in bibliometric studies should be viewed with careful consideration to learn of any influencing factors. (6) Use of INIS has predominance in Japan, and use of ECD has predominance in the U.S. Users from developed and developing countries assigned as the Member State of IAEA would be better served using INIS and ECD as the intellectual data source. As the recent trend, WOS and SCOPUS are used as the evaluation tools. (author)

Advanced concepts, analysis approaches and criteria for nuclear piping system design

International Nuclear Information System (INIS)

Tang, H.T.; Tagart, S.W. Jr.; Tang, Y.K.

1992-01-01

Recent research in piping system design and analysis has resulted in advancements on damping values, independent support motion (ISM), static coefficient method, simplified inelastic method and ASME code criteria changes. In the support area, passive type of supports such as energy-absorbing device and gap stopper have been developed. These advancements provide bases for improved and cost-effective design of future nuclear piping systems. (author)

Nuclear Data Libraries for Advanced Systems - Fusion Devices (FENDL-3). Summary report from the Second Research Coordination Meeting

International Nuclear Information System (INIS)

Sawan, Mohamed E.

2010-06-01

The second Research Co-ordination Meeting of the Nuclear Data Libraries for Advanced Systems - Fusion Devices (FENDL - 3) was held at the IAEA Headquarters in Vienna from 23 to 26 March 2010. A summary of the meeting is given in this report along with the discussions which took place. An important outcome of the meeting was the decision to provide ENDF data libraries (FENDL-3/T) by April 2011. Finally, a list of task assignments was prepared together with the plan for future CRP activities. (author)

The United States Advanced Reactor Technologies Research and Development Program

International Nuclear Information System (INIS)

O’Connor, Thomas J.

2014-01-01

The following aspects are addressed: • Nuclear energy mission; • Reactor research development and deployment (RD&D) programs: - Light Water Reactor Sustainability Program; - Small Modular Reactor Licensing Technical Support; - Advanced Reactor Technologies (ART)

Nuclear Data Libraries for Advanced Systems - Fusion Devices (FENDL 3.0). Summary report of the Third Research Coordination Meeting

International Nuclear Information System (INIS)

Sawan, Mohamed E.

2012-03-01

The third Research Co-ordination Meeting of the Nuclear Data Libraries for Advanced Systems - Fusion Devices (FENDL-3) was held at IAEA Headquarters in Vienna from 6 to 9 December 2011. A summary of the presentations given during meeting is given in this report along with the discussions that took place. A list of actions necessary to complete the library production, processing and testing are given. Details of the documents arising from the CRP were agreed. (author)

Recent Advances in Computational Methods for Nuclear Magnetic Resonance Data Processing

KAUST Repository

Gao, Xin

2013-01-11

Although three-dimensional protein structure determination using nuclear magnetic resonance (NMR) spectroscopy is a computationally costly and tedious process that would benefit from advanced computational techniques, it has not garnered much research attention from specialists in bioinformatics and computational biology. In this paper, we review recent advances in computational methods for NMR protein structure determination. We summarize the advantages of and bottlenecks in the existing methods and outline some open problems in the field. We also discuss current trends in NMR technology development and suggest directions for research on future computational methods for NMR.

Large screen mimic display design research for advanced main control room in nuclear power plant

International Nuclear Information System (INIS)

Zheng Mingguang; Yang Yanhua; Xu Jijun; Zhang Qinshun; Ning Zhonghe

2002-01-01

Firstly the evolution of mimic diagrams or displays used in the main control room of nuclear power plant was introduced. The active functions of mimic diagrams were analyzed on the release of operator psychological burden and pressure, the assistance of operator for the information searching, status understanding, manual actuation, correct decision making as well as the safe and reliable operation of the nuclear power plant. The importance and necessity to use the (large screen) mimic diagrams in advanced main control room of nuclear power plant, the design principle, design details and verification measures of large screen mimic display are also described

Advances in nuclear science and technology

CERN Document Server

Henley, Ernest J

1962-01-01

Advances in Nuclear Science and Technology, Volume 1 provides an authoritative, complete, coherent, and critical review of the nuclear industry. This book covers a variety of topics, including nuclear power stations, graft polymerization, diffusion in uranium alloys, and conventional power plants.Organized into seven chapters, this volume begins with an overview of the three stages of the operation of a power plant, either nuclear or conventionally fueled. This text then examines the major problems that face the successful development of commercial nuclear power plants. Other chapters consider

Education in nuclear science at IPEN - CNEN, Sao Paulo, Brazil. Advanced School of Nuclear Energy-EAEN

International Nuclear Information System (INIS)

Semmler, R.; Catharino, M.G.M.; Vasconcellos, M.B.A.

2012-01-01

EAEN (Advanced School of Nuclear Energy, 2010) is an annual school that consists of a week of activities in the area of Nuclear Physics, Radiochemistry and uses of Nuclear Energy for a public made of high school students. The EAEN project represents a pioneering program on science education and dissemination of knowledge, conducted by researchers and focused mainly on high school and scientific education for the population in general. The school's priority is to explore the failures and the lack of education in the dissemination of nuclear energy for high school students as well as to attract prospective students with great potential for graduate courses of IPEN and other institutions in Sao Paulo and in Brazil. (author)

Annual report of Nuclear Science Research Institute, JFY2006

International Nuclear Information System (INIS)

2008-03-01

Nuclear Science Research Institute (NSRI) is composed of Planning and Coordination Office and seven departments such as Department of Operational Safety Administration, Department of Radiation Protection, Department of Research Reactor and Tandem Accelerator, Department of Hot Laboratories and Facilities, Department of Criticality and Fuel Cycle Research Facilities, Department of Decommissioning and Waste Management, and Engineering Services Department. This annual report of JFY2006 summarizes the activities of NSRI, the R and D activities of the Research and Development Directorates and human resources development at site, and is expected to be referred to and utilized by R and D departments and project promotion sectors at NSRI site for the enhancement of their own research and management activities to attain their goals according to 'Middle-term Plan' successfully and effectively. In chapter 1, outline of JFY2006 activities of NSRI is described. In chapter 2, the following activities made by the departments in NSRI are summarized, i.e., (1) operation and maintenance of research reactors (JRR-3, JRR-4, NSRR), criticality assemblies (STACY, TRACY, FCA, TCA), hot laboratories (BECKY, Reactor Fuel Examination Facility, WASTEF, Research Laboratory 4, Plutonium Research Laboratory 1, Tokai Hot Laboratory, etc), and large-scale facilities (Tandem accelerator, LSTF, THYNC, TPTF, etc), and (2) safety management, radiation protection, management of radioactive wastes, decommissioning of nuclear facilities, engineering services, utilities and maintenance, etc, all of which are indispensable for the stable and safe operation and utilization of the research facilities. The technical developments for the advancement of the related technologies are also summarized. In chapter 3, the R and D and human resources development activities are described including the topics of the research works and projects performed by the Research and Development Directorates at site, such as

Experimental research on passive residual heat remove system for advanced PWR

International Nuclear Information System (INIS)

Huang Yanping; Zhuo Wenbin; Yang Zumao; Xiao Zejun; Chen Bingde

2003-01-01

The experimental and qualified results of MISAP in the research of passive residual heat remove system of advanced PWR performed in the Bubble physics and natural circulation laboratory in Nuclear Power Institute of China in the past ten years is overviewed. Further researches for engineering research and design are also suggested

Utilization technique for advanced nuclear materials database system Data-Free-Way'

International Nuclear Information System (INIS)

Fujita, Mitsutane; Kurihara, Yutaka; Kinugawa, Junichi; Kitajima, Masahiro; Nagakawa, Josei; Yamamoto, Norikazu; Noda, Tetsuji; Yagi, Koichi; Ono, Akira

2001-01-01

Four organizations the National Research Institute for Metals (NRIM), the Japan Atomic Energy Research Institute (JAERI), the Japan Nuclear Fuel Cycle Development Institute (JNC) and Japan Science and Technology Incorporation (JST), conducted the 2nd period joint research for the purpose of development of utilization techniques for advanced nuclear materials database system named 'Data-Free-Way' (DFW), to make more useful system to support research and development of the nuclear materials, from FY 1995 to FY 1999. NRIM intended to fill a data system on diffusion and nuclear data by developing utilization technique on diffusion informations of steels and aluminum and nuclear data for materials for its independent system together with participating in fulfil of the DFW. And, NRIM has entered to a project on wide area band circuit application agreed at the G7 by using technologies cultivated by NRIM, to investigate network application technology with the Michigan State University over the sea under cooperation assistant business of JST, to make results on CCT diagram for welding and forecasting of welding heat history accumulated at NRIM for a long term, to perform development of a simulator assisting optimum condition decision of welding. (G.K.)

On the safety performance of the advanced nuclear energy systems

International Nuclear Information System (INIS)

Li Shounan

1999-01-01

Some features on the safety performances of the Advanced Nuclear Energy Systems are discussed. The advantages and some peculiar problems on the safety of Advanced Nuclear Energy Systems with subcritical nuclear reactor driven by external neutron sources are also pointed out in comparison with conventional nuclear reactors

Research on advanced aqueous reprocessing of spent nuclear fuel: literature study

Energy Technology Data Exchange (ETDEWEB)

Van Hecke, K.; Goethals, P.

2006-07-15

The goal of the partitioning and transmutation strategy is to reduce the radiotoxicity of spent nuclear fuel to the level of natural uranium in a short period of time (about 1000 years) and thus the required containment period of radioactive material in a repository. Furthermore, it aims to reduce the volume of waste requiring deep geological disposal and hence the associated space requirements and costs. Several aqueous as well as pyrochemical separation processes have been developed for the partitioning of the long-lived radionuclides from the remaining of the spent fuel. This report aims to describe and compare advanced aqueous reprocessing methods.

Research on advanced aqueous reprocessing of spent nuclear fuel: literature study

International Nuclear Information System (INIS)

Van Hecke, K.; Goethals, P.

2006-01-01

The goal of the partitioning and transmutation strategy is to reduce the radiotoxicity of spent nuclear fuel to the level of natural uranium in a short period of time (about 1000 years) and thus the required containment period of radioactive material in a repository. Furthermore, it aims to reduce the volume of waste requiring deep geological disposal and hence the associated space requirements and costs. Several aqueous as well as pyrochemical separation processes have been developed for the partitioning of the long-lived radionuclides from the remaining of the spent fuel. This report aims to describe and compare advanced aqueous reprocessing methods.

A study on improving international political and diplomatic acceptability of advanced nuclear fuel cycle for Korea

International Nuclear Information System (INIS)

Lee, Joeng Hoon

2011-03-01

In order to establish an advanced nuclear fuel cycle program for Korea, U.S. support and trust are imperative. In the midst of the negotiations for the renewal of the U.S.-South Korea agreement on peaceful nuclear cooperation, the two obvious components of an advanced nuclear fuel cycle - enrichment and reprocessing - have surfaced as major issues. Despite the United States' firm commitment to nonproliferation, South Korea is in dire need to advance its nuclear fuel cycle proportionate to its now significant nuclear energy program. This research project's objective is to put the U.S.-South Korea Nuclear Agreement into proper alliance perspective. The military alliance between the two countries have weathered decades of trials and tribulations. It is one of the most staunch alliances in existence in global politics. As such, the negotiations for the nuclear agreement must be dealt with in the context of the broader alliance relations, not to be lost in the technicalities of the nonproliferation arguments. But even so, South Korea's track record is far better than some of the states the United States has recently granted a most lenient nuclear agreement - India being a case in point. Fairness issue also surfaces when it comes to the agreement the United States has concluded with Japan. As an equally if not more important ally in Asia, South Korea must be permitted to make significant advancements in either enrichment or reprocessing procedures. This project argues that this is the appropriate direction given the history of the two nations' alliance relations. In the final analysis, this research puts forward the argument that the matter that should count the most is not the question of whether South Korea will proliferate or not, but rather whether the United States trusts its battle-tested ally, enough to help develop a peaceful and efficient advanced nuclear fuel cycle program in South Korea

Managing nuclear safety research facilities and capabilities in a changing nuclear industry: the contribution of the OECD/NEA

International Nuclear Information System (INIS)

Royen, J.

2000-01-01

Although the safety level of nuclear power plants in OECD countries is very satisfactory and the technologies basic to the resolution of safety issues have advanced considerably, continued nuclear safety research work is necessary to address many of the residual concerns, and it remains an important element in ensuring the safe operation of nuclear power plants. However, the funding levels of national Government safety research programmes have been reduced over recent years. There is concern about the ability of OECD Member countries to sustain an adequate level of nuclear safety research capability. The OECD/NEA has a key role to play in organizing reflection and exchange of information on the most efficient use of available technical resources, and in the international management of nuclear safety research facilities and capabilities in a changing nuclear industry. Possible initiatives are mentioned in the paper. (author)

Proceedings of the NATO Advanced Research Workshop on Nuclear Power and Energy Security

International Nuclear Information System (INIS)

Apikyan, S.; Diamond, D.

2010-01-01

The purpose of this NATO workshop is to contribute to the critical assessment of how to prepare for a new national nuclear energy program, and to make recommendations for future action. In addition, our goal is to promote close working relationships between technical people from different countries and with different professional expertise. In particular, the countries that are involved in this workshop are those from NATO and those from the Partner countries such as those in the Commonwealth of Independent States. A NATO workshop is not an international conference or symposium but rather a forum for advanced level, intensive discussions. The presentations are part of the growing font of knowledge on the subject of how to develop a national nuclear energy program. It is heard about the infrastructure that is needed and how the IAEA and countries with existing experience are helping to provide that infrastructure to those working toward a nuclear energy program. It is heard about the experiences of several countries embarking on new nuclear development, with an emphasis on how progress is being made in Armenia. It is also heard about the potential for using small and medium size reactors; something not being pursued by the countries with large nuclear programs

A Study on intensifying efficiency for international collaborative development of Advanced Nuclear Energy Technology

Energy Technology Data Exchange (ETDEWEB)

Chang, Moon Hee; Kim, H. R.; Kim, H. J.; Chang, J. H.; Hahn, D. H.; Bae, Y. Y.; Kim, W. W.; Jeong, I.; Lee, D. S.; Lee, J. H. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2008-06-15

Generation IV International Forum(GIF), where 13 countries including Korea collaborate to develop future nuclear energy systems, put into force 'Generation IV International Forum Project Arrangement' in 2007 for the international research and development of Gen IV Systems, following the entry into force of Framework Agreement in 2005. The International Nuclear Research Initiative(I-NERI) between Korea and United States and the International Project on Innovative Nuclear Energy Systems and Fuel Cycles(INPRO) of IAEA are continued in this year, produced lots of visible outcomes. These international activities have a common goal of the collaborative development of advanced nuclear system technologies but differ in the main focusing areas and aspects, so Korea needs to establish the integrated strategy based on the distinguished and complementary approach for the participation of each international programs, as examples the GIF for the advanced system technology development, INPRO for the set-up of institution and infra-structure, and I-NERI for the access of the core technologies and acquisition of the transparency of nuclear R and D.

A Study on intensifying efficiency for international collaborative development of Advanced Nuclear Energy Technology

International Nuclear Information System (INIS)

Chang, Moon Hee; Kim, H. R.; Kim, H. J.; Chang, J. H.; Hahn, D. H.; Bae, Y. Y.; Kim, W. W.; Jeong, I.; Lee, D. S.; Lee, J. H.

2008-06-01

Generation IV International Forum(GIF), where 13 countries including Korea collaborate to develop future nuclear energy systems, put into force 'Generation IV International Forum Project Arrangement' in 2007 for the international research and development of Gen IV Systems, following the entry into force of Framework Agreement in 2005. The International Nuclear Research Initiative(I-NERI) between Korea and United States and the International Project on Innovative Nuclear Energy Systems and Fuel Cycles(INPRO) of IAEA are continued in this year, produced lots of visible outcomes. These international activities have a common goal of the collaborative development of advanced nuclear system technologies but differ in the main focusing areas and aspects, so Korea needs to establish the integrated strategy based on the distinguished and complementary approach for the participation of each international programs, as examples the GIF for the advanced system technology development, INPRO for the set-up of institution and infra-structure, and I-NERI for the access of the core technologies and acquisition of the transparency of nuclear R and D

Gordon Conference on Nuclear Research

International Nuclear Information System (INIS)

Austin, S.M.

1983-09-01

Session topics were: quarks and nuclear physics; anomalons and anti-protons; the independent particle structure of nuclei; relativistic descriptions of nuclear structure and scattering; nuclear structure at high excitation; advances in nuclear astrophysics; properties of nuclear material; the earliest moments of the universe; and pions and spin excitations in nuclei

Thermal-hydraulics associated with nuclear education and research

International Nuclear Information System (INIS)

Yokobori, Seiichi

2011-01-01

This article was the rerecording of the author's lecture at the fourth 'Future Energy Forum' (aiming at improving nuclear safety and economics) held in December 2010. The lecture focused on (1) importance of thermal hydraulics associated with nuclear education and research (critical heat flux, two-phase flow and multiphase flow), (2) emerging trend of maintenance engineering (fluid induced vibration, flow accelerated corrosion and stress corrosion cracks), (3) fostering sensible nuclear engineer with common engineering sense, (4) balanced curriculum of basics and advanced research, (5) computerized simulation and fluid mechanics, (6) crucial point of thermo hydraulics education (viscosity, flux, steam and power generation), (7) safety education and human resources development (indispensable technologies such as defence in depth) and (8) topics of thermo hydraulics research (vortices of curbed pipes and visualization of two-phase flow). (T. Tanaka)

Filling the gaps in SCWR materials research: advanced nuclear corrosion research facilities in Hamilton

International Nuclear Information System (INIS)

Krausher, J.L.; Zheng, W.; Li, J.; Guzonas, D.; Botton, G.

2011-01-01

Research efforts on materials selection and development in support of the design of supercritical water-cooled reactors (SCWRs) have produced a considerable amount of data on corrosion, creep and other related properties. Summaries of the data on corrosion [1] and stress corrosion cracking [2] have recently been produced. As research on the SCWR advances, gaps and limitations in the published data are being identified. In terms of corrosion properties, these gaps can be seen in several areas, including: 1) the test environment, 2) the physical and chemical severity of the tests conducted as compared with likely reactor service/operating conditions, and 3) the test methods used. While some of these gaps can be filled readily using existing facilities, others require the availability of advanced test facilities for specific tests and assessments. In this paper, highlights of the new materials research facilities jointly established in Hamilton by CANMET Materials Technology Laboratory and McMaster University are presented. (author)

X-ray spectroscopy of highly ionized heavy ions as an advanced research for controlled nuclear fusion power

International Nuclear Information System (INIS)

Zschornack, G.; Musiol, G.

1988-01-01

Diagnostics and modelling of nuclear fusion plasmas require a detailed knowledge of atomic and molecular data for highly ionized heavy ions. Experimental verification of atomic data is made on the basis of IAEA recommendations using the method of high-resolution wavelength-dispersive X-ray spectroscopy in order to obtain contributions extensioning the available atomic data lists. Basic facilities for producing highly charged heavy ions are the electron-ion rings of the heavy ion collective accelerator and the electron beam ion source KRYON-2 at the Joint Institute for Nuclear Research at Dubna. For high-resolution X-ray spectroscopy with these sources a computer-aided crystal diffraction spectrometer has been developed the precision of which is achieved by using advanced principles of measurement and control. Relativistic atomic structure calculations have been carried out for a great number of elements and configurations to obtain data in ionization regions heavily accessible to the experiment. (author)

Development of the Advanced Nuclear Safety Information Management (ANSIM) System

Energy Technology Data Exchange (ETDEWEB)

Sohn, Jae Min; Ko, Young Cheol; Song, Tai Gil [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2012-05-15

Korea has become a technically independent nuclear country and has grown into an exporter of nuclear technologies. Thus, nuclear facilities are increasing in significance at KAERI (Korea Atomic Energy Research Institute), and it is time to address the nuclear safety. The importance of nuclear safety cannot be overemphasized. Therefore, a management system is needed urgently to manage the safety of nuclear facilities and to enhance the efficiency of nuclear information. We have established ISP (Information Strategy Planning) for the Integrated Information System of nuclear facility and safety management. The purpose of this paper is to develop a management system for nuclear safety. Therefore, we developed the Advanced Nuclear Safety Information Management system (hereinafter referred to as the 'ANSIM system'). The ANSIM system has been designed and implemented to computerize nuclear safety information for standardization, integration, and sharing in real-time. Figure 1 shows the main home page of the ANSIM system. In this paper, we describe the design requirements, contents, configurations, and utilizations of the ANSIM system

Nuclear Research and Development Capabilities Needed to Support Future Growth

Energy Technology Data Exchange (ETDEWEB)

Wham, Robert M. [ORNL, P.O. Box 2008, Oak Ridge, TN 37831-6154 (United States); Kearns, Paul [Battelle Memorial Institute (United States); Marston, Ted [Marston Consulting (United States)

2009-06-15

The energy crisis looming before the United States can be resolved only by an approach that integrates a 'portfolio' of options. Nuclear energy, already an important element in the portfolio, should play an even more significant role in the future as the U.S. strives to attain energy independence and reduce carbon emissions. The DOE Office of Nuclear Energy asked Battelle Memorial Institute to obtain input from the commercial power generation industry on industry's vision for nuclear energy over the next 30-50 years. With this input, Battelle was asked to generate a set of research and development capabilities necessary for DOE to support the anticipated growth in nuclear power generation. This presentation, based on the report generated for the Office of Nuclear Energy, identifies the current and future nuclear research and development capabilities required to make this happen. The capabilities support: (1) continued, safe operation of the current fleet of nuclear plants; (2) the availability of a well qualified and trained workforce; (3) demonstration of the next generation nuclear plants; (4) development of a sustainable fuel cycle; (5) advanced technologies for maximizing resource utilization and minimization of waste and (6) advanced modeling and simulation for rapid and reliable development and deployment of new nuclear technologies. In order to assure these capabilities are made available, a Strategic Nuclear Energy Capability Initiative is proposed to provide the required resources during this critical period of time. (authors)

Status Report on Structural Materials for Advanced Nuclear Systems

International Nuclear Information System (INIS)

Allen, T.R.; Balbaud-Celerier, F.; Asayama, T.; Pouchon, M.; Busby, J.T.; Maloy, S.; Park, J.Y.; Fazio, C.; Dai, Y.; Agostini, P.; Chevalier, J.P.; Marrow, J.

2013-01-01

Materials performance is critical to the safe and economic operation of any nuclear system. As the international community pursues the development of Generation IV reactor concepts and accelerator-driven transmutation systems, it will be increasingly necessary to develop advanced materials capable of tolerating the more challenging environments of these new systems. The international community supports numerous materials research programmes, with each country determining its individual focus on a case-by-case basis. In many instances, similar alloys of materials systems are being studied in several countries, providing the opportunity for collaborative and cross-cutting research that benefits different systems. This report is a snapshot of the current materials programmes supporting the development of advanced concepts. The descriptions of the research are grouped by concept, and national programmes are described within each concept. The report provides an overall sense of the importance of materials research worldwide and the opportunities for synergy among the countries represented in this overview. (authors)

Research on evacuation planning as nuclear emergency preparedness

International Nuclear Information System (INIS)

Yamamoto, Kazuya

2007-10-01

The International Atomic Energy Agency (IAEA) has introduced new concepts of precautionary action zone (PAZ) and urgent protective action planning zone (UPZ) in 'Preparedness and Response for a Nuclear or Radiological Emergency' (GS-R-2 (2002)), in order to reduce substantially the risk of severe deterministic health effects. Open literature based research was made to reveal problems on evacuation planning and the preparedness for nuclear emergency arising from introduction of PAZ into Japan that has applied the emergency planning zone (EPZ) concept currently. In regard to application of PAZ, it should be noted that the requirements for preparedness and response for a nuclear or radiological emergency are not only dimensional but also timely. The principal issue is implementation of evacuation of precautionary decided area within several hours. The logic of evacuation planning for a nuclear emergency and the methods of advance public education and information in the U.S. is effective for even prompt evacuation to the outside of the EPZ. As concerns evacuation planning for a nuclear emergency in Japan, several important issues to be considered were found, that is, selection of public reception centers which are outside area of the EPZ, an unique reception center assigned to each emergency response planning area, public education and information of practical details about the evacuation plan in advance, and necessity of the evacuation time estimates. To establish a practical evacuation planning guide for nuclear emergencies, further researches on application of traffic simulation technology to evacuation time estimates and on knowledge of actual evacuation experience in natural disasters and chemical plant accidents are required. (author)

Recent advances in nuclear cardiology

DEFF Research Database (Denmark)

Gutte, H.; Petersen, C. Leth; Kjaer, A.

2008-01-01

Nuclear cardiology is an essential part of functional, non-invasive, cardiac imaging. Significant advances have been made in nuclear cardiology since planar (201)thallium ((201)TI) scintigraphy was introduced for the evaluation of left ventricular (LV) perfusion nearly 40 years ago. The use...... of nuclear cardiology has been steadily increasing over the last 20 years with important steps being the introduction of (99m)technetium- ((99m)Tc)-labelled perfusion radiotracers, the change from only planar to now much more single photon emission computed tomography (SPECT) and positron emission tomography...... (PET), electrocardiogram gating of nuclear perfusion imaging, and finally introducing nuclear hybrid imaging using either SPECT or PET together with either computed tomography or magnetic resonance imaging. The indications have extended from nearly only coronary artery diseases to several non...

Idaho National Laboratory - Nuclear Research Center

International Nuclear Information System (INIS)

Zaidi, M.K.

2005-01-01

Full text: The Idaho National Laboratory is committed to the providing international nuclear leadership for the 21st Century, developing and demonstrating compiling national security technologies, and delivering excellence in science and technology as one of the United States Department of Energy's (DOE) multiprogram national laboratories. INL runs three major programs - Nuclear, Security and Science. nuclear programs covers the Advanced test reactor, Six Generation technology concepts selected for R and D, Targeting tumors - Boron Neutron capture therapy. Homeland security - Homeland Security establishes the Control System Security and Test Center, Critical Infrastructure Test Range evaluates technologies on a scalable basis, INL conducts high performance computing and visualization research and science - INL facility established for Geocentrifuge Research, Idaho Laboratory, a Utah company achieved major milestone in hydrogen research and INL uses extremophile bacteria to ease bleaching's environmental cost. To provide leadership in the education and training, INL has established an Institute of Nuclear Science and Engineering (Inset). The institute will offer a four year degree based on a newly developed curriculum - two year of basic science course work and two years of participation in project planning and development. The students enrolled in this program can continue to get a masters or a doctoral degree. This summer Inset is the host for the training of the first international group selected by the World Nuclear University (WNU) - 75 fellowship holders and their 30 instructors from 40 countries. INL has been assigned to provide future global leadership in the field of nuclear science and technology. Here, at INL, we keep safety first above all things and our logo is 'Nuclear leadership synonymous with safety leadership'

Status report on research on advanced fundamental engineering in 1999

International Nuclear Information System (INIS)

2000-07-01

JNC (Japan Nuclear Cycle Development Institute) has been promoting the cooperative research program on advanced fundamental engineering with the Japanese Universities. It is the 5th year of this program on 1999. JNC has been calling for the research themes of utilizing the equipment and facilities of JNC, which must be the leading research for the JNC projects. The expert committee has selected the issues from the applications of the universities; This report includes the list of the researches and individual summaries implemented in 1999, in which total 49 issues are categorized in the three fields, these are, fast breeder reactor, nuclear fuel cycle, and environment technology. The 26 issues are included in the field of fast breeder reactor. Topics in this area are neutron beam technology to measure voids, laser technology to detect failed fuel, ultra-sonic velocity meter to estimate passive cooling characteristics, behavior of sodium coolant in accidents, physics on TRU fuel, and mechanical and/or chemical characteristics on irradiated solid metals, ceramics and liquids. The 9 issues are included in the field of nuclear fuel cycle. Topics in this area are chemical erosion of material, computerized simulation on actinide by molecular orbit model, chemical stability on advanced reprocessing, laser technology to measure fuel particles, decomposition of fluoride oil, advanced dose evaluation. The 9 issues are included in the field of environment technology. Topics in this area are behavior of underground water, radioactivity ecology of plants, biochemical activities of microbes in deep bedrock. The individual report describes the title, related personnel, its time schedule, objectives, facilities, status, and references in the prearranged format. (Tanaka, T.)

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

Student involvement and research for the nuclear industry

International Nuclear Information System (INIS)

Ginniff, M.E.

1980-01-01

Nuclear engineering is one of the modern and rapidly advancing technologies. Those already involved in it are continually updating their knowledge to keep abreast of the developments. Of course the sound basic principles of engineering still apply but the scene of application can be transformed in a few years. In fact, because of this, many engineers from more traditional industries often express the view that presently the total range of nuclear engineering is research and development. How can students be trained for such a rapidly advancing technology. Is not the answer early involvement. Effective early involvement for students can only come about by the close co-operation and involvement of the staff of universities and industry. The theme is developed. (author)

Commercializing the next generation: the AP600 advanced simplified nuclear power plant

International Nuclear Information System (INIS)

Bruschi, H.J.

1994-01-01

Today, government and industry are working together on advanced nuclear power plant designs that take advantage of valuable lessons learned from the experience to date and promise to reconcile the demands of economic expansion with the laws of environmental protection. In the U.S., the Department of Energy (DOE) and the Electric Power Research Institute (EPRI) initiated a design certification program in 1989 to develop and commercialize advanced light water reactors (ALWRs) for the next round of power plant construction. Advanced, simplified technology is one approach under development to end the industry's search for a simpler, more forgiving, and less costly reactor. As part of this program, Westinghouse is developing the AP600, a new standard 600 MWe advanced, simplified plant. The design strikes a balance between the use of proven technology and new approaches. The result is a greatly streamlined plant that can meet safety regulations and reliability requirements, be economically competitive, and promote broader public confidence in nuclear energy. 1 fig

Advanced Nuclear Magnetic Resonance

OpenAIRE

Alonso, Diego A.

2014-01-01

Transparencias en inglés de la asignatura "Resonancia Magnética Nuclear Avanzada" (Advanced Nuclear Magnetic Resonance) (36643) que se imparte en el Máster de Química Médica como asignatura optativa de 3 créditos ECTS. En esta asignatura se completa el estudio iniciado en la asignatura de quinto curso de la licenciatura en Química "Determinación estructural" (7448) y en la del Grado de Química de tercer curso "Determinación estructural de los compuestos orgánicos" (26030) en lo referente a té...

Experiences and Trends of Manufacturing Technology of Advanced Nuclear Fuels

International Nuclear Information System (INIS)

2012-08-01

The 'Atoms for Peace' mission initiated in the mid-1950s paved the way for the development and deployment of nuclear fission reactors as a source of heat energy for electricity generation in nuclear power reactors and as a source of neutrons in non-power reactors for research, materials irradiation, and testing and production of radioisotopes. The fuels for nuclear reactors are manufactured from natural uranium (∼99.3% 238 U + ∼0.7% 235 U) and natural thorium (∼100% 232 Th) resources. Currently, most power and research reactors use 235 U, the only fissile isotope found in nature, as fuel. The fertile isotopes 238 U and 232 Th are transmuted in the reactor to human-made 239 Pu and 233 U fissile isotopes, respectively. Likewise, minor actinides (MA) (Np, Am and Cm) and other plutonium isotopes are also formed by a series of neutron capture reactions with 238 U and 235 U. Long term sustainability of nuclear power will depend to a great extent on the efficient, safe and secure utilization of fissile and fertile materials. Light water reactors (LWRs) account for more than 82% of the operating reactors, followed by pressurized heavy water reactors (PHWRs), which constitute ∼10% of reactors. LWRs will continue to dominate the nuclear power market for several decades, as long as economically viable natural uranium resources are available. Currently, the plutonium obtained from spent nuclear fuel is subjected to mono recycling in LWRs as uranium-plutonium mixed oxide (MOX), containing up to 12% PuO 2 , in a very limited way. The reprocessed uranium (RepU) is also re-enriched and recycled in LWRs in a few countries. Unfortunately, the utilization of natural uranium resources in thermal neutron reactors is 2 and MOX fuel technology has matured during the past five decades. These fuels are now being manufactured, used and reprocessed on an industrial scale. Mixed uranium- plutonium monocarbide (MC), mononitride (MN) and U-Pu-Zr alloys are recognized as advanced fuels

Utilization technique for advanced nuclear materials database system Data-Free-Way'

Energy Technology Data Exchange (ETDEWEB)

Fujita, Mitsutane; Kurihara, Yutaka; Kinugawa, Junichi; Kitajima, Masahiro; Nagakawa, Josei; Yamamoto, Norikazu; Noda, Tetsuji; Yagi, Koichi; Ono, Akira [National Research Inst. for Metals, Tsukuba, Ibaraki (Japan)

2001-02-01

Four organizations the National Research Institute for Metals (NRIM), the Japan Atomic Energy Research Institute (JAERI), the Japan Nuclear Fuel Cycle Development Institute (JNC) and Japan Science and Technology Incorporation (JST), conducted the 2nd period joint research for the purpose of development of utilization techniques for advanced nuclear materials database system named 'Data-Free-Way' (DFW), to make more useful system to support research and development of the nuclear materials, from FY 1995 to FY 1999. NRIM intended to fill a data system on diffusion and nuclear data by developing utilization technique on diffusion informations of steels and aluminum and nuclear data for materials for its independent system together with participating in fulfil of the DFW. And, NRIM has entered to a project on wide area band circuit application agreed at the G7 by using technologies cultivated by NRIM, to investigate network application technology with the Michigan State University over the sea under cooperation assistant business of JST, to make results on CCT diagram for welding and forecasting of welding heat history accumulated at NRIM for a long term, to perform development of a simulator assisting optimum condition decision of welding. (G.K.)

Outline of research project on nuclear fusion, 1985

International Nuclear Information System (INIS)

Uchida, Taijiro

1985-08-01

When the advance of nuclear fusion research during 10 years hereafter is predicted, the next project should start the research toward nuclear burning, adopt the diversified ways, and develop the research in wide related fields. The central subject such as the containment of plasma is studies with large experimental facilities, but in the related fields, the research subsidies must be utilized positively. The organization to perform the research compries 6 groups, 1) reactor materials and plasma-wall interactions 2) science and engineering of tritium, and influence on living things, 4) development of superconducting magnets, 5) fusion blanket engineering, and 6) design and assessment of thermonuclear reactors. The distribution and management of the scientific research subsidy are explained. All of the subjects of planned and publicly invited research a listed, and the researchers concerned, the amount of subsidy, the objective and the plan of execution in fiscal year 1984 of each research are outlined. (J.P.N.)

Outline of research project on nuclear fusion, 1984

International Nuclear Information System (INIS)

Uchida, Taijiro

1984-08-01

When the advance of nuclear fusion research during 10 years hereafter is predicted, the next project should start the research toward nuclear burning, adopt the diversified ways, a nd develop the research in wide related fields. The central subject such as the containment of plasma is studies with large experimental facilities, but in the related fields, the research subsidies must be utilized positively. The organization to perform the research compries 6 groups, 1) reactor materials and plasma-wall interaction, 2) science and engineering of tritium and influence on living things, 3) fundamentals of core control, 4) development of superconducting magnets, 5) fusion blanket engineering, and 6) design and assessment of thermonuclear reactors. The distribution and management of the scientific research subsidy are explained. All of the subjects of planned and publicly invited research a listed, and the researchers concerned, the amount of subsidy, the objective and the plan of execution in fiscal 1983 of each research are outlined. (J.P.N.)

Idaho national laboratory - a nuclear research center

International Nuclear Information System (INIS)

Zaidi Mohammed, K.

2006-01-01

Full text: The Idaho National Laboratory (INL) is committed to providing international nuclear leadership for the 21st Century, developing and demonstrating compelling national security technologies, and delivering excellence in science and technology as one of the United States Department of Energy's (DOE) multi program national laboratories. INL runs three major programs - Nuclear, Security and Science. Nuclear programs covers the Advanced test reactor, Six Generation IV technology concepts selected for Rand D, targeting tumors - Boron Neutron Capture therapy. Homeland Security establishes the Control System Security and Test Center, Critical Infrastructure Test Range evaluates technologies on a scalable basis, INL conducts high performance computing and visualization research and science. To provide leadership in the education and training, INL has established an Institute of Nuclear Science and Engineering (INSE) under the Center for Advanced Energy Studies (CAES) and the Idaho State University (ISU). INSE will offer a four year degree based on a newly developed curriculum - two year of basic science course work and two years of participation in project planning and development. The students enrolled in this program can continue to get a masters or a doctoral degree. This summer INSE is the host for the training of the first international group selected by the World Nuclear University (WNU) - 75 fellowship holders and their 30 instructors from 40 countries. INL has been assigned to provide future global leadership in the field of nuclear science and technology. Here, at INL, we keep safety first above all things and our logo is 'Nuclear leadership synonymous with safety leadership'. (author)

Research-based approaches to nuclear education

Energy Technology Data Exchange (ETDEWEB)

Donev, J.M.K.C., E-mail: jason.donev@ucalgary.ca [Univ. of Calgary, Calgary, AB (Canada); Carpenter, Y., E-mail: ycarpenter@gmail.com [Univ.ty of Colorado at Boulder, Boulder, CO (United States)

2014-07-01

Teaching nuclear power requires an expert to communicate a significant number of abstract concepts from diverse disciplines, and assemble these into a larger intellectual framework for the students. Scholarly education research, particularly in individual science disciplines, has provided significant advances in teaching core subject material by breaking away from traditional lecturing. Thus far, however,little work has applied these results to introductory nuclear power classes. This paper explores a method of engaging introductory nuclear students deeply by using a combination of Socratic and mastery methods of teaching. Students develop conceptual understanding of the material through the group work and the use of diverse resources, including textbooks, online references, and computer models that encourage free exploration of these concepts. Marks have improved considerably, and students engage with the material at a significantly deeper level than in previous lecture-based iterations of this course. (author)

Research-based approaches to nuclear education

International Nuclear Information System (INIS)

Donev, J.M.K.C.; Carpenter, Y.

2014-01-01

Teaching nuclear power requires an expert to communicate a significant number of abstract concepts from diverse disciplines, and assemble these into a larger intellectual framework for the students. Scholarly education research, particularly in individual science disciplines, has provided significant advances in teaching core subject material by breaking away from traditional lecturing. Thus far, however,little work has applied these results to introductory nuclear power classes. This paper explores a method of engaging introductory nuclear students deeply by using a combination of Socratic and mastery methods of teaching. Students develop conceptual understanding of the material through the group work and the use of diverse resources, including textbooks, online references, and computer models that encourage free exploration of these concepts. Marks have improved considerably, and students engage with the material at a significantly deeper level than in previous lecture-based iterations of this course. (author)

Advanced teleoperation in nuclear applications

International Nuclear Information System (INIS)

Hamel, W.R.; Feldman, M.J.; Martin, H.L.

1984-01-01

A new generation of integrated remote maintenance systems is being developed to meet the needs of future nuclear fuel reprocessing at the Oak Ridge National Laboratory. Development activities cover all aspects of an advanced teleoperated maintenance system with particular emphasis on a new force-reflecting servomanipulator concept. The new manipulator, called the advanced servomanipulator, is microprocessor controlled and is designed to achieve force-reflection performance near that of mechanical master/slave manipulators. The advanced servomanipulator uses a gear-drive transmission which permits modularization for remote maintainability (by other advanced servomanipulators) and increases reliability. Human factors analysis has been used to develop an improved man/machine interface concept based upon colorgraphic displays and menu-driven tough screens. Initial test and evaluation of two advanced servomanipulator slave arms and several other development components have begun. 9 references, 5 figures

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

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

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.)

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

Advanced nuclear control and protection system ANCAP-80

International Nuclear Information System (INIS)

Asai, Takashi; Okano, Michihiko; Ishibashi, Kengo; Hasegawa, Masakoto; Fukuda, Hiroyoshi; Hosomichi, Renichi.

1983-01-01

Advanced reactor protection systems were developed to improve operational reliability and availability and to ease the burden of operators of Mitsubishi PWR Nuclear Power Stations. (Called ANCAP-80; Advanced Nuclear Control And Protection System) For the PWR plants now being planned and in future plans, Mitsubishi will adopt these systems with the following functional features; (1) Four channel protection logic, (2) Automatic bypass logic, (3) Automatic test provision, (4) Optical isolators. (author)

Contributions of the National Institute of Nuclear Research to the advance of Science and Technology in Mexico. Commemorative edition 2010

International Nuclear Information System (INIS)

Duque M, G.; Jimenez R, M.; Monroy G, F.; Romero H, S.; Serment G, J.

2010-01-01

From the second decade of the X X century the applications of the nuclear energy have been important part of the scientific and technological patrimony in Mexico. Records exist with regard to the use of the radioisotopes and the radiations in our country in that time, and in a formal way until the year of 1950, in a process that culminates with the creation of the Comision Nacional de Energia Nuclear (CNEN. January 1, 1956). In January 12, 1972 were published the Organic Law that created to the Instituto Nacional de Energia Nuclear, being responsible for the works that the CNEN developed. The current Instituto Nacional de Investigaciones Nucleares (ININ) was constituted starting from the Regulation Law of the constitutional Article 27 in nuclear matter of January 26, 1979, abrogated and substituted by the Law in force of February 4, 1985. In this lapse they were undertaken multitude of projects with results and diverse achievements. From their creation, the mission of the ININ and the previous institutions has been to realize research in science and nuclear technology, to promote their peaceful uses and to diffuse the achieved advances, always searching for to link them to the economic, social, scientific and technological development of the country. In this occasion with the purpose of participating in the commemoration of the bicentennial of the independence and centennial of the Mexican revolution in our country, the ININ decided to publish this work, directed to a wide public, with the intention of providing a vision the most complete and appropriate possible of the activities in research and technology that it is carries out at the moment. This work also seeks to be a diffusion instrument of the tasks that they are carried out in the institute, in diverse subjects as: the basic research, the nuclear applications in the health, the agriculture and the industry, the studies on the contamination and the environment; the dosimetry; the radiological protection; as

Advances in chemical engineering in nuclear and process industries

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-06-01

Symposium on Advances in Chemical Engineering in Nuclear and Process Industries dealt with a wide spectrum of areas encompassing various industries such as nuclear, fertilizer, petrochemical, refinery and cement. The topics covered in the symposium dealt with the advancements in the existing fields of science and technologies as well as in some of the emerging technologies such as membrane technology, bio-chemical and photo-chemical engineering etc. with a special emphasis on nuclear related aspects. Papers relevant to INIS are indexed separately.

Advances in chemical engineering in nuclear and process industries

International Nuclear Information System (INIS)

1994-06-01

Symposium on Advances in Chemical Engineering in Nuclear and Process Industries dealt with a wide spectrum of areas encompassing various industries such as nuclear, fertilizer, petrochemical, refinery and cement. The topics covered in the symposium dealt with the advancements in the existing fields of science and technologies as well as in some of the emerging technologies such as membrane technology, bio-chemical and photo-chemical engineering etc. with a special emphasis on nuclear related aspects. Papers relevant to INIS are indexed separately

Advances in nuclear science and technology

CERN Document Server

Greebler, Paul

1968-01-01

Advances in Nuclear Science and Technology Volume 4 provides information pertinent to the fundamental aspects of advanced reactor concepts. This book discusses the advances in various areas of general applicability, including modern perturbation theory, optimal control theory, and industrial application of ionizing radiations.Organized into seven chapters, this volume begins with an overview of the technology of sodium-cooled fast breeder power reactors and gas-cooled power reactors. This text then examines the key role of reactor safety in the development of fast breeder reactors. Other chapt

Proceeding of the Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology part II : Nuclear Chemistry, Process Technology, Radioactive Waste Management and Environment

International Nuclear Information System (INIS)

Sukarsono, R.; Ganang Suradjijo

2002-01-01

Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology is a routine activity held by Centre for Research and Development of Advanced Technology, National Nuclear Energy Agency, for monitoring the research activity which achieved in National Nuclear Energy Agency. This proceedings contains a proposal about basic research in nuclear technology which has environment. This proceedings is the second part of the two parts which published in series. There are 57 articles which have separated index. (PPIN)

Fuel rod bundles proposed for advanced pressure tube nuclear reactors

International Nuclear Information System (INIS)

Prodea, Iosif; Catana, Alexandru

2010-01-01

The paper aims to be a general presentation for fuel bundles to be used in Advanced Pressure Tube Nuclear Reactors (APTNR). The characteristics of such a nuclear reactor resemble those of known advanced pressure tube nuclear reactors like: Advanced CANDU Reactor (ACR TM -1000, pertaining to AECL) and Indian Advanced Heavy Water Reactor (AHWR). We have also developed a fuel bundle proposal which will be referred as ASEU-43 (Advanced Slightly Enriched Uranium with 43 rods). The ASEU-43 main design along with a few neutronic and thermalhydraulic characteristics are presented in the paper versus similar ones from INR Pitesti SEU-43 and CANDU-37 standard fuel bundles. General remarks regarding the advantages of each fuel bundle and their suitability to be burned in an APTNR reactor are also revealed. (authors)

Design study on advanced nuclear fuel recycling system by pyrometallurgical reprocessing technology

Energy Technology Data Exchange (ETDEWEB)

Kasai, Yoshimitsu; Kakehi, Isao; Moro, Satoshi; Tobe, Kenji; Kawamura, Fumio; Higashi, Tatsuhiro; Yonezawa, Shigeaki [Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center; Yoshiuji, Takahiro

1998-12-01

The Japan Nuclear Fuel Cycle Development Institute is conducting research and development on the nuclear fuel recycling system, which will improve the economy, safety, and environmental impact of the nuclear fuel recycling system in the age of the FBR. The System Engineering Division in the O-arai Engineering Center has conducted a design study on an advanced nuclear fuel recycling system for FBRs by using pyrometallurgical reprocessing technology. The system is an economical and compact module-type system, and can be used for reprocessing oxide fuel and also new types of fuel (metal fuel and nitride fuel). This report describes the concept of this system and results of the design study. (author)

Design study on advanced nuclear fuel recycling system by pyrometallurgical reprocessing technology

International Nuclear Information System (INIS)

Kasai, Yoshimitsu; Kakehi, Isao; Moro, Satoshi; Tobe, Kenji; Kawamura, Fumio; Higashi, Tatsuhiro; Yonezawa, Shigeaki; Yoshiuji, Takahiro

1998-01-01

The Japan Nuclear Fuel Cycle Development Institute is conducting research and development on the nuclear fuel recycling system, which will improve the economy, safety, and environmental impact of the nuclear fuel recycling system in the age of the FBR. The System Engineering Division in the O-arai Engineering Center has conducted a design study on an advanced nuclear fuel recycling system for FBRs by using pyrometallurgical reprocessing technology. The system is an economical and compact module-type system, and can be used for reprocessing oxide fuel and also new types of fuel (metal fuel and nitride fuel). This report describes the concept of this system and results of the design study. (author)

Nuclear research reactors

International Nuclear Information System (INIS)

1985-01-01

It's presented data about nuclear research reactors in the world, retrieved from the Sien (Nuclear and Energetic Information System) data bank. The information are organized in table forms as follows: research reactors by countries; research reactors by type; research reactors by fuel and research reactors by purpose. (E.G.) [pt

Trends in Nuclear Explosion Monitoring Research & Development - A Physics Perspective

Energy Technology Data Exchange (ETDEWEB)

Maceira, Monica [Los Alamos National Laboratory; Blom, Philip Stephen [Los Alamos National Laboratory; Maccarthy, Jonathan K. [Los Alamos National Laboratory; Marcillo, Omar Eduardo [Los Alamos National Laboratory; Euler, Garrett Gene [Los Alamos National Laboratory; Begnaud, Michael Lee [Los Alamos National Laboratory; Ford, Sean R. [Lawrence Livermore National Laboratory; Pasyanos, Michael E. [Lawrence Livermore National Laboratory; Orris, Gregory J. [Naval Research Laboratory; Foxe, Michael P. [Pacific Northwest National Laboratory; Arrowsmith, Stephen J. [Sandia National Laboratory; Merchant, B. John [Sandia National Laboratory; Slinkard, Megan E. [Sandia National Laboratory

2017-06-01

This document entitled “Trends in Nuclear Explosion Monitoring Research and Development – A Physics Perspective” reviews the accessible literature, as it relates to nuclear explosion monitoring and the Comprehensive Nuclear-Test-Ban Treaty (CTBT, 1996), for four research areas: source physics (understanding signal generation), signal propagation (accounting for changes through physical media), sensors (recording the signals), and signal analysis (processing the signal). Over 40 trends are addressed, such as moving from 1D to 3D earth models, from pick-based seismic event processing to full waveform processing, and from separate treatment of mechanical waves in different media to combined analyses. Highlighted in the document for each trend are the value and benefit to the monitoring mission, key papers that advanced the science, and promising research and development for the future.

Annual report of Nuclear Science Research Institute, JFY2005

International Nuclear Information System (INIS)

2007-04-01

research facilities. The technical developments for the advancement of the related technologies are also summarized. In chapter 3, the R and D activities are described including the topics of the research works and projects performed by the Research and Development Directorates at site, such as Nuclear Safety Research Center, Advanced Science Research Center, Nuclear Science and Engineering Directorate, and Quantum Beam Science Directorate, at NSRI. (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

Advanced physical protection systems for nuclear materials

International Nuclear Information System (INIS)

Jones, O.E.

1976-01-01

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

Advanced physical protection systems for nuclear materials

International Nuclear Information System (INIS)

Jones, O.E.

1975-10-01

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

Framatome advanced nuclear power-benefits for our clients from the new company

International Nuclear Information System (INIS)

Weber, P.

2001-01-01

Framatome ANP (Advanced Nuclear Power) merges the complementary strengths of two global nuclear industry leaders Framatome and Siemens - offering clients the best technological solutions for safe, reliable and economical plant performance. With a combined workforce of 13,300 skilled individuals, Framatome ANP is now the nuclear industry's leading supplier. Serving as Original Equipment Manufacturer (OEM) for more than 90 reactors that provide about 30% of the world's total installed nuclear power capacity, our experienced resources remain focused on the local needs of individual clients, wherever in the world they may be. The Company main business used to be turnkey construction of complete Nuclear Power plants, BWR and PWR capabilities, heavy equipment manufacturing, comprehensive I and C capabilities, and also expertise and knowledge of VVER. Framatome ANP will benefit in all of its fields of activity of the experience gained through Framatome and Siemens' collaboration on the next generation reactor, the EPR, as well as on steam generators replacements and or modernization of VVER. Framatome ANP nuclear fuel designs for both PWR and BWR plants provide innovative features and world-leading performance. Framatome ANP is organized according a matrix organization with: - 4 Business Groups (Project and Engineering, Service, Nuclear Fuel, Mechanical Equipment) - 3 Regional Divisions (Framatome Advanced Nuclear Power S.A.S., France; Framatome Advanced Nuclear Power GmbH, Germany; Framatome Advanced Nuclear Power Inc., USA). By 30th January 2001 Siemens Nuclear Power GmbH, founded in 2000 as successor of the Nuclear Division of Siemens Power Generation Group (KWU), was renamed to Framatome Advanced Nuclear Power GmbH forming the German part of the world wide acting company. Over the past 40 years 23 nuclear power plants all around the world - not only pressurized and boiling water reactors, but also two heavy-watermoderated reactors have been designed, constructed and

RECENT ACTIVITIES AT THE CENTER FOR SPACE NUCLEAR RESEARCH FOR DEVELOPING NUCLEAR THERMAL ROCKETS

International Nuclear Information System (INIS)

O'Brien, Robert C.

2001-01-01

Nuclear power has been considered for space applications since the 1960s. Between 1955 and 1972 the US built and tested over twenty nuclear reactors/ rocket-engines in the Rover/NERVA programs. However, changes in environmental laws may make the redevelopment of the nuclear rocket more difficult. Recent advances in fuel fabrication and testing options indicate that a nuclear rocket with a fuel form significantly different from NERVA may be needed to ensure public support. The Center for Space Nuclear Research (CSNR) is pursuing development of tungsten based fuels for use in a NTR, for a surface power reactor, and to encapsulate radioisotope power sources. The CSNR Summer Fellows program has investigated the feasibility of several missions enabled by the NTR. The potential mission benefits of a nuclear rocket, historical achievements of the previous programs, and recent investigations into alternatives in design and materials for future systems will be discussed.

A Strategy for Nuclear Energy Research and Development

International Nuclear Information System (INIS)

Bennett, Ralph G.

2008-01-01

The United States is facing unprecedented challenges in climate change and energy security. President-elect Obama has called for a reduction of CO2 emissions to 1990 levels by 2020, with a further 80% reduction by 2050. Meeting these aggressive goals while gradually increasing the overall energy supply requires that all non-emitting technologies must be advanced. The development and deployment of nuclear energy can, in fact, help the United States meet several key challenges: (1) Increase the electricity generated by non-emitting sources to mitigate climate change, (2) Foster the safe and proliferation-resistant use of nuclear energy throughout the world, (3) Reduce the transportation sector's dependence on imported fossil fuels, and (4) Reduce the demand on natural gas for process heat and hydrogen production. However, because of the scale, cost, and time horizons involved, increasing nuclear energy's share will require a coordinated research effort-combining the efforts of industry and government, supported by innovation from the research community. This report outlines the significant nuclear energy research and development (R and D) necessary to create options that will allow government and industrial decision-makers to set policies and create nuclear energy initiatives that are decisive and sustainable. The nuclear energy R and D strategy described in this report adopts the following vision: Safe and economical nuclear energy in the United States will expand to address future electric and non-electric needs, significantly reduce greenhouse gas emissions and provide energy diversity, while providing leadership for safe, secure and responsible expansion of nuclear energy internationally

Thermal-Hydraulic Experiments and Modelling for Advanced Nuclear Reactor Systems

International Nuclear Information System (INIS)

Song, C. H.; Baek, W. P.; Chung, M. K.

2007-06-01

The objectives of the project are to study thermal hydraulic characteristics of advanced nuclear reactor system for evaluating key thermal-hydraulic phenomena relevant to new safety concepts. To meet the research goal, several thermal hydraulic experiments were performed and related thermal hydraulic models were developed with the experimental data which were produced through the thermal hydraulic experiments. The Followings are main research topics: - Multi-dimensional Phenomena in a Reactor Vessel Downcomer - Condensation-induced Thermal Mixing in a Pool - Development of Thermal-Hydraulic Models for Two-Phase Flow - Construction of T-H Data Base

Cancer risks near nuclear facilities: the importance of research design and explicit study hypotheses.

Science.gov (United States)

Wing, Steve; Richardson, David B; Hoffmann, Wolfgang

2011-04-01

In April 2010, the U.S. Nuclear Regulatory Commission asked the National Academy of Sciences to update a 1990 study of cancer risks near nuclear facilities. Prior research on this topic has suffered from problems in hypothesis formulation and research design. We review epidemiologic principles used in studies of generic exposure-response associations and in studies of specific sources of exposure. We then describe logical problems with assumptions, formation of testable hypotheses, and interpretation of evidence in previous research on cancer risks near nuclear facilities. Advancement of knowledge about cancer risks near nuclear facilities depends on testing specific hypotheses grounded in physical and biological mechanisms of exposure and susceptibility while considering sample size and ability to adequately quantify exposure, ascertain cancer cases, and evaluate plausible confounders. Next steps in advancing knowledge about cancer risks near nuclear facilities require studies of childhood cancer incidence, focus on in utero and early childhood exposures, use of specific geographic information, and consideration of pathways for transport and uptake of radionuclides. Studies of cancer mortality among adults, cancers with long latencies, large geographic zones, and populations that reside at large distances from nuclear facilities are better suited for public relations than for scientific purposes.

Proceedings of the 2004 international congress on advances in nuclear power plants - ICAPP'04

International Nuclear Information System (INIS)

2004-01-01

The 2004 International Congress on Advances in Nuclear Power Plants (ICAPP'04) provides a forum for the industry to exchange the latest ideas and research findings on nuclear plants from all perspectives. This conference builds on the success of last year's meeting held in Cordoba, Spain, and on the 2002 inaugural meeting held in Hollywood, Florida. Because of the hard work of many volunteers from around the world, ICAPP'04 has been successful in achieving its goal. More than 325 invited and contributed papers/presentations are part of this ICAPP. There are 5 invited plenary sessions and 70 technical sessions with contributed papers. The ICAPP'04 Proceedings contain almost 275 papers prepared by authors from 25 countries covering topics related to advances in nuclear power plant technology. The program by technical track deals with: 1 - Water-Cooled Reactor Programs and Issues (Status of All New Water-Cooled Reactor Programs; Advanced PWRs: Developmental Stage I; Advanced PWRs: Developmental Stage II; Advanced PWRs: Basic Design Stage; Advanced BWRs; Economics, Regulation, Licensing, and Construction; AP1000); 2 - High Temperature Gas Cooled Reactors (Pebble Bed Modular Reactors; Very High Temperature Reactors; HTR Fuels and Materials; Innovative HTRs and Fuel Cycles); 3 - Long Term Reactor Programs and Strategies (Supercritical Pressure Water Reactors; Lead-Alloy Fast Reactors; Sodium and Gas Fast Reactors; Status of Advanced Reactor Programs; Non-classical Reactor Concepts); 4 - Operation, Performance, and Reliability Management (Information Technology Effect on Plant Operation; Operation, Maintenance and Reliability; Improving Performance and Reducing O and M Costs; Plant Modernization and Retrofits); 5 - Plant Safety Assessment and Regulatory Issues (LOCA and non-LOCA Analysis Methodologies; LOCA and non-LOCA Plant Analyses; In-Vessel Retention; Containment Performance and Hydrogen Control; Advances in Severe Accident Analysis; Advances in Severe Accident

Nuclear Research and Development in the AEC Era

International Nuclear Information System (INIS)

Mongkolnavin, R.

2014-01-01

In 2015, South East Asian Countris are entering into the social, economic and security partnership. Nuclear Research and Development undoubtedly has important roles in all three pillars. Nuclear applications that are being realised in the region ranges from energy, mrdical to agricultural application.In this new era of cooperation, we are seeking for technologies that lead to solution to improve our ways of living. As all other research and development nuclear research has been carried out in all countries in the region. However, it does have its critiques on safety issues based on people capability in the region. In order to make progress in research and development, human resource development is the key fundamental to its sucess. An experience of regional collaboration in developing pulsed neutron souurce is presented as an example. The research had been revived though collaoration of different research laboratories within ASEAN countries with support of Asian African Assosiation for Plasma Training (AAAPT). The 'low cost research theme' has fundamentally set up a platform for more future advanced research for fusion and for local industrial applications. It also increases experimental and theoretical research awareness among new generations that could be carried out in local laboratories. A device such as UNU-ICPT Plasma Focus has been explored, and it has been built, studied; both theoretical and experimental; and used for many different kind of applications.

Advancing Ethical Neuroscience Research.

Science.gov (United States)

Borah, B Rashmi; Strand, Nicolle K; Chillag, Kata L

2016-12-01

As neuroscience research advances, researchers, clinicians, and other stakeholders will face a host of ethical challenges. The Presidential Commission for the Study of Bioethical Issues (Bioethics Commission) has published two reports that provide recommendations on how to advance research endeavors ethically. The commission addressed, among other issues, how to prioritize different types of neuroscience research and how to include research participants who have impaired consent capacity. The Bioethics Commission's recommendations provide a foundation for ethical guidelines as neuroscience research advances and progresses. © 2016 American Medical Association. All Rights Reserved.

Thermal hydraulic tests for reactor safety system -Research on the improvement of nuclear safety-

International Nuclear Information System (INIS)

Chung, Moon Ki; Park, Chun Kyeong; Yang, Seon Kyu; Chung, Chang Hwan; Chun, Shee Yeong; Song, Cheol Hwa; Chun, Hyeong Gil; Chang, Seok Kyu; Chung, Heung Joon; Won, Soon Yeon; Cho, Yeong Ro; Kim, Bok Deuk; Min, Kyeong Ho

1994-07-01

The present research aims at the development of the thermal hydraulic verification test technology for the reactor safety system of the conventional and advanced nuclear power plant and the development of the advanced thermal hydraulic measuring techniques. (Author)

Research and Development on nuclear fission

International Nuclear Information System (INIS)

2007-01-01

Research and development activities on advanced and innovative reactors are performed within a domestic programme and international initiatives. The ongoing New Nuclear Fission National Programme is synergic and complementary to the International Nuclear Energy Initiative (INERI) and EURATOM framework programmes and is managed by ENEA through a specific agreement signed in June 2007 by the Italian Ministry for Economic Development (MSE). The activities concern an integral advanced pressurised light-water-cooled reactor (IRIS nuclear power plant [NPP]) and several Generation-4. fast reactors: lead-cooled, very high temperature and sodium-cooled. A summary of the main results achieved in 2007 follows. In the framework of the INERI programme ENEA and other Italian organisations are involved in the design of the International Reactor Innovative and Secure (IRIS NPP), particularly in the design certification. An appropriate integral testing programme will be performed in the SPES-3 facility to be built at the SIET laboratories in Piacenza. The facility will be located inside the building of the decommissioned Emilia oil-fired power plant. Once erected, the facility will simulate IRIS at full height, full pressure and temperature, and with volumes and power scaled by factors of 1:100 and 1:150, respectively. The activity will be carried out in a collaboration with Oak Ridge National Laboratory (ORNL), USA under an international initiative concerning cooperation in the field of nuclear-related technologies of mutual interest. In 2007 activities were mainly devoted to the conceptual design of the SPES-3 facility, the development of SPES-3 nodalization and the seismic isolation analysis of the IRIS auxiliary building

Technical verification of advanced nuclear fuel for KSNPs

International Nuclear Information System (INIS)

Lee, C. B.; Bang, J. G.; Kim, D. H. and others

2002-03-01

KNFC has developed the advanced 16x16 fuel assembly for the Korean Standard Nuclear Plants through the three-year R and D project (from April 1999 to March 2002) under the Nuclear R and D program by MOST. The purpose of this project is to verify the advanced 16x16 fuel assembly for the Korean Standard Nuclear Plants being developed by KNFC during the same period. Verification tests for the advanced fuel assembly and its components such as characteristic test on the spacer grid spring and dimple, static buckling and dynamic impact test on the 5x5 partial spacer grid, the fuel rod vibration test supported by the PLUS7 mid-spacer grid, fretting wear test, turbulent flow structure test in wind tunnel and corrosion test were performed by using the KAERI facilities. Design reports and test results produced by KNFC were technically reviewed. For the domestic production of burnable poison rod, manufacturing technology of burnable poison pellets was developed

Proceedings of the 2008 International Congress on Advances in Nuclear Power Plants - ICAPP '08

International Nuclear Information System (INIS)

2008-01-01

ICAPP 2008 congress brought together international experts of the nuclear industry involved in the operation, development, building, regulation and research related to Nuclear Power Plants. The program covered the full spectrum of Nuclear Power Plant issues from design, deployment and construction of plants to research and development of future designs and advanced systems. It covered also lessons learned from power, research and demonstration reactors from over 50 years of experience with operation and maintenance, structures, materials, technical specifications, human factors, system design and reliability. The program comprised 13 technical tracks: 1. Water-Cooled Reactor Programs and Issues: Evolutionary designs, innovative, passive, light and heavy water cooled reactors; issues related to meeting near term utility needs; design issues; business, economical cost challenges; infrastructure limitations and improved construction techniques including modularization. 2. High Temperature Gas Cooled Reactors: Design and development issues, components and materials, safety, reliability, economics, demonstration plants and environmental issues, fuel design and reliability, power conversion technology, impact of non electricity applications on reactor design; advanced thermal and fast reactors. 3. LMFR and Longer Term Reactor Programs: Reactor technology with enhanced fuel cycle features for improved resource utilization, waste characteristics, and power conversion capabilities. Potential reactor designs with longer development times such as super critical water reactors and liquid fuel reactors, Gen IV, INPRO, EUR and other programs. 4. Operation, Performance and Reliability Management: Training, O and M costs, life cycle management, risk based maintenance, operational experiences, performance and reliability improvements, outage optimization, human factors, plant staffing, outage reduction features, major component reliability, repair and replacement, in

Advanced Ultrafast Spectroscopy for Chemical Detection of Nuclear Fuel Cycle Materials

International Nuclear Information System (INIS)

Villa-Aleman, E.; Houk, A.; Spencer, W.

2017-01-01

The development of new signatures and observables from processes related to proliferation activities are often related to the development of technologies. In our physical world, the intensity of observables is linearly related to the input drivers (light, current, voltage, etc.). Ultrafast lasers with high peak energies, opens the door to a new regime where the intensity of the observables is not necessarily linear with the laser energy. Potential nonlinear spectroscopic applications include chemical detection via remote sensing through filament generation, material characterization and processing, chemical reaction specificity, surface phenomena modifications, X-ray production, nuclear fusion, etc. The National Security Directorate laser laboratory is currently working to develop new tools for nonproliferation research with femtosecond and picosecond lasers. Prior to this project, we could only achieve laser energies in the 5 nano-Joule range, preventing the study of nonlinear phenomena. To advance our nonproliferation research into the nonlinear regime we require laser pulses in the milli-Joule (mJ) energy range. We have procured and installed a 35 fs-7 mJ laser, operating at one-kilohertz repetition rate, to investigate elemental and molecular detection of materials in the laboratory with potential applications in remote sensing. Advanced, nonlinear Raman techniques will be used to study materials of interest that are in a matrix of many materials and currently with these nonlinear techniques we can achieve greater than three orders of magnitude signal enhancement. This work studying nuclear fuel cycle materials with nonlinear spectroscopies will advance SRNL research capabilities and grow a core capability within the DOE complex.

Advanced Ultrafast Spectroscopy for Chemical Detection of Nuclear Fuel Cycle Materials

Energy Technology Data Exchange (ETDEWEB)

Villa-Aleman, E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Houk, A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Spencer, W. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-09-29

The development of new signatures and observables from processes related to proliferation activities are often related to the development of technologies. In our physical world, the intensity of observables is linearly related to the input drivers (light, current, voltage, etc.). Ultrafast lasers with high peak energies, opens the door to a new regime where the intensity of the observables is not necessarily linear with the laser energy. Potential nonlinear spectroscopic applications include chemical detection via remote sensing through filament generation, material characterization and processing, chemical reaction specificity, surface phenomena modifications, X-ray production, nuclear fusion, etc. The National Security Directorate laser laboratory is currently working to develop new tools for nonproliferation research with femtosecond and picosecond lasers. Prior to this project, we could only achieve laser energies in the 5 nano-Joule range, preventing the study of nonlinear phenomena. To advance our nonproliferation research into the nonlinear regime we require laser pulses in the milli-Joule (mJ) energy range. We have procured and installed a 35 fs-7 mJ laser, operating at one-kilohertz repetition rate, to investigate elemental and molecular detection of materials in the laboratory with potential applications in remote sensing. Advanced, nonlinear Raman techniques will be used to study materials of interest that are in a matrix of many materials and currently with these nonlinear techniques we can achieve greater than three orders of magnitude signal enhancement. This work studying nuclear fuel cycle materials with nonlinear spectroscopies will advance SRNL research capabilities and grow a core capability within the DOE complex.

Russian MINATOM nuclear safety research strategic plan. An international review

International Nuclear Information System (INIS)

1999-03-01

The 'Safety Research Strategic Plan for Russian Nuclear Power Plants' was published in draft form at the Russian International Nuclear Safety Centre (RINSC) by a working group of fifteen senior Russian experts. The Plan consists of 12 chapters, each addressing a specific technical area and containing a number of proposed research programmes and projects to advance the state-of-knowledge in that area. In part because a strong Recommendation to undertake such a Plan was made by the 1998 OECD/NEA study, the OECD Nuclear Energy Agency was asked by the Director of RINSC and the Director of USINSC to organize an international review of the Plan when the English-language version became available in October, 1998. This report represents the results of that review. (R.P.)

Advanced alarm system design and human performance: Guidance development and current research

Energy Technology Data Exchange (ETDEWEB)

O` Hara, J M [Brookhaven National Lab., Upton, NY (United States)

1997-09-01

This paper describes a research program sponsored by the U.S. Nuclear Regulatory Commission to address the human factors engineering (HFE) aspects of nuclear power plant alarm systems. The overall objective of the program is to develop HFE review guidance for advanced alarm systems. Guidance has been developed based on a broad base of technical and research literature. As part of the development effort, aspects of alarm system design for which the technical basis was insufficient to support guidance development were identified and prioritized. Research is currently underway to address the highest priority topics: alarm processing and display characteristics. (author). 29 refs, 2 figs.

Advanced alarm system design and human performance: Guidance development and current research

International Nuclear Information System (INIS)

O'Hara, J.M.

1997-01-01

This paper describes a research program sponsored by the U.S. Nuclear Regulatory Commission to address the human factors engineering (HFE) aspects of nuclear power plant alarm systems. The overall objective of the program is to develop HFE review guidance for advanced alarm systems. Guidance has been developed based on a broad base of technical and research literature. As part of the development effort, aspects of alarm system design for which the technical basis was insufficient to support guidance development were identified and prioritized. Research is currently underway to address the highest priority topics: alarm processing and display characteristics. (author). 29 refs, 2 figs

Nuclear Explosion Monitoring Research and Engineering Program - Strategic Plan

Energy Technology Data Exchange (ETDEWEB)

Casey, Leslie A. [DOE/NNSA

2004-09-01

The Department of Energy (DOE)/National Nuclear Security Administration (NNSA) Nuclear Explosion Monitoring Research and Engineering (NEM R&E) Program is dedicated to providing knowledge, technical expertise, and products to US agencies responsible for monitoring nuclear explosions in all environments and is successful in turning scientific breakthroughs into tools for use by operational monitoring agencies. To effectively address the rapidly evolving state of affairs, the NNSA NEM R&E program is structured around three program elements described within this strategic plan: Integration of New Monitoring Assets, Advanced Event Characterization, and Next-Generation Monitoring Systems. How the Program fits into the National effort and historical accomplishments are also addressed.

State of controlled nuclear fusion research

International Nuclear Information System (INIS)

Rodrigo, A.B.

1978-04-01

The development of a commercial fusion reactor requires an adequate solution to the problems of heating and confinement of the nuclear fuel, as well as a considerable effort in materials technology and reactor engineering. A general discussion is presented of the status of the research connected with the most advanced concepts, indicating in each case the present situation and the main problems that must be solved to meet the requeriments estimated for power reactors. In particular, the laser-inertial concept is reviewed in detail. (author) [es

Perspectives for nuclear structure research at GSI: from halo nuclei to superheavy elements

Energy Technology Data Exchange (ETDEWEB)

Muenzenberg, G.

1997-11-01

After a brief overview on recent advances in the investigation of nuclei at the driplines and the upper end of the nuclear table key issues of nuclear structure research as adressed by new theoretical developments will be discussed in context with new developments in heavy-ion accelerators and experimental techniques. (orig.)

Perspectives for nuclear structure research at GSI--from halo nuclei to superheavy elements

International Nuclear Information System (INIS)

Munzenberg, G.

1997-01-01

After a brief overview on recent advances in the investigation of nuclei at the drip lines and the upper end of the nuclear table key issues of nuclear structure research as addressed by new theoretical developments will be discussed in context with new developments in heavy-ion accelerators and experimental techniques

Research on artificial intelligence systems for nuclear installations

International Nuclear Information System (INIS)

Sakuma, Minoru

1992-01-01

The development and utilization of atomic energy in Japan has be advanced in conformity with the long term plan of atomic energy development and utilization decided in 1987. As one of the basic targets, the upbringing of creative and innovative science and technology is put up. Artificial intelligence technology has been positioned as one of the important basic technologies for promoting future atomic energy development. The research and development of artificial intelligence technology have been advanced aiming at making nuclear power stations autonomous, by the guidance of Science and Technology Agency and the cooperation of several research institutes. The upbringing of creative science and technology, the preponderant development of basic technology, the concept of developing the basic technology for atomic energy, the concept of autonomous plants, the standard for autonomy, the approach to autonomous plants, the present state of the researches in respective research institutes on autonomous operation and autonomous maintenance are described. (K.I.)

NIH Research: Advances in Parkinson's Disease Research

Science.gov (United States)

... of this page please turn JavaScript on. NIH Research: Advances in Parkinson's Disease Research Past Issues / Winter 2014 Table of Contents Story ... Photo courtesy of NIH Advances in Parkinson's Disease Research Story Landis, Ph.D., has been Director of ...

Computer Security for Commercial Nuclear Power Plants - Literature Review for Korea Hydro Nuclear Power Central Research Institute

Energy Technology Data Exchange (ETDEWEB)

Duran, Felicia Angelica [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Security Systems Analysis Dept.; Waymire, Russell L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Security Systems Analysis Dept.

2013-10-01

Sandia National Laboratories (SNL) is providing training and consultation activities on security planning and design for the Korea Hydro and Nuclear Power Central Research Institute (KHNPCRI). As part of this effort, SNL performed a literature review on computer security requirements, guidance and best practices that are applicable to an advanced nuclear power plant. This report documents the review of reports generated by SNL and other organizations [U.S. Nuclear Regulatory Commission, Nuclear Energy Institute, and International Atomic Energy Agency] related to protection of information technology resources, primarily digital controls and computer resources and their data networks. Copies of the key documents have also been provided to KHNP-CRI.

Computer Security for Commercial Nuclear Power Plants - Literature Review for Korea Hydro Nuclear Power Central Research Institute

International Nuclear Information System (INIS)

Duran, Felicia Angelica; Waymire, Russell L.

2013-01-01

Sandia National Laboratories (SNL) is providing training and consultation activities on security planning and design for the Korea Hydro and Nuclear Power Central Research Institute (KHNPCRI). As part of this effort, SNL performed a literature review on computer security requirements, guidance and best practices that are applicable to an advanced nuclear power plant. This report documents the review of reports generated by SNL and other organizations [U.S. Nuclear Regulatory Commission, Nuclear Energy Institute, and International Atomic Energy Agency] related to protection of information technology resources, primarily digital controls and computer resources and their data networks. Copies of the key documents have also been provided to KHNP-CRI.

Securing personnel in nuclear fuel cycle research and development in Japan

International Nuclear Information System (INIS)

Sekino, H.

1993-01-01

The PNC, a japanese governmental research and development organization, is concerned with research and development into building and operating advanced power reactors and R and D into the whole cycle of the nuclear fuel. PNC promotes international cooperation with the USA and European countries as well as technical cooperation with the private sectors in uranium enrichment, reprocessing and advanced reactor development. This report discusses the current situation and problems in securing PNC personnel, in securing 'loan' staff for PNC, and in personnel exchanges for technical transfer and international cooperation. 5 figs

Progress of experimental research on nuclear safety in NPIC

Energy Technology Data Exchange (ETDEWEB)

Gong, Houjun; Zan, Yuanfeng; Peng, Chuanxin; Xi, Zhao; Zhang, Zhen; Wang, Ying; He, Yanqiu; Huang, Yanping [Nuclear Power Institute of China, Chengdu (China)

2016-05-15

Two kinds of Generation III commercial nuclear power plants have been developed in CNNC (China National Nuclear Corporation), one is a small modular reactor ACP100 having an equivalent electric power 100 MW, and the other is HPR1000 (once named ACP1000) having an equivalent electric power 1 000 MW. Both NPPs widely adopted the design philosophy of advanced passive safety systems and considered the lessons from Fukushima Daichi nuclear accident. As the backbone of the R and D of ACP100 and HPR1000, NPIC (Nuclear power Institute of China) has finished the engineering verification test of main safety systems, including passive residual heat removal experiments, reactor cavity injection experiments, hydrogen combustion experiments, and passive autocatalytic recombiner experiments. Above experimental work conducted in NPIC and further research plan of nuclear safety are introduced in this paper.

Advanced control systems to improve nuclear power plant reliability and efficiency

International Nuclear Information System (INIS)

1997-07-01

The TECDOC is the result of a series of an advisory and consultants meetings held by the IAEA in 1995-1996 in Vienna (March 1995), in Erlangen Germany (December 1995), in Garching, Germany (June 1996) and in Vienna (November 1996). It was prepared with the participation and contributions of experts from Austria, Canada, Finland, France, Germany, the Republic of Korea, Norway, the Russian Federation, the United Kingdom and the United States of America. The publication not only describes advanced control systems for the improvement of nuclear power plant reliability and efficiency, but also provides a road map to guide interested readers to plan and execute an advanced instrumentation and control project. The subjects include: identification of needs and requirements, justification for safety and user acceptance, and the development of an engineering process. The report should be of interest to nuclear power plant staff, I and C system designers and integrators as well as regulators and researchers. Refs, figs, tabs

R and D perspectives on the advanced nuclear safety regulation system

International Nuclear Information System (INIS)

Lee, Chang Ju; Ahn, Sang Kyu; Park, Jong Seuk; Chung, Dae Wook; Han, Sang Hoon; Lee, Jung Won

2009-01-01

As current licensing process is much desired to be optimized both plant safety and regulatory efficiency, an advanced safety regulation such as risk informed regulation has been come out. Also, there is a need to have a future oriented safety regulation since a lot of new reactors are conceptualized. Keeping pace with these needs, since early 2007, Korean government has launched a new project for preparing an advanced and future oriented nuclear safety regulation system. In order to get practical achievements, the project team sets up such specific research objectives for the development of: implementation program for graded regulation using risk and performance information; multi purpose PSA models for regulatory uses; a technology neutral regulatory framework for future innovative reactors; evaluation procedure of proliferation resistance; and, performance based fire hazard analysis method and evaluation system. This paper introduces major R and D outputs of this project, and provides some perspectives for achieving effectiveness and efficiency of the nuclear regulation system in Korea

R and D perspectives on the advanced nuclear safety regulation system

Energy Technology Data Exchange (ETDEWEB)

Lee, Chang Ju; Ahn, Sang Kyu; Park, Jong Seuk; Chung, Dae Wook [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of); Han, Sang Hoon; Lee, Jung Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2009-04-15

As current licensing process is much desired to be optimized both plant safety and regulatory efficiency, an advanced safety regulation such as risk informed regulation has been come out. Also, there is a need to have a future oriented safety regulation since a lot of new reactors are conceptualized. Keeping pace with these needs, since early 2007, Korean government has launched a new project for preparing an advanced and future oriented nuclear safety regulation system. In order to get practical achievements, the project team sets up such specific research objectives for the development of: implementation program for graded regulation using risk and performance information; multi purpose PSA models for regulatory uses; a technology neutral regulatory framework for future innovative reactors; evaluation procedure of proliferation resistance; and, performance based fire hazard analysis method and evaluation system. This paper introduces major R and D outputs of this project, and provides some perspectives for achieving effectiveness and efficiency of the nuclear regulation system in Korea.

Advanced control systems to improve nuclear power plant reliability and efficiency

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-07-01

The TECDOC is the result of a series of an advisory and consultants meetings held by the IAEA in 1995-1996 in Vienna (March 1995), in Erlangen Germany (December 1995), in Garching, Germany (June 1996) and in Vienna (November 1996). It was prepared with the participation and contributions of experts from Austria, Canada, Finland, France, Germany, the Republic of Korea, Norway, the Russian Federation, the United Kingdom and the United States of America. The publication not only describes advanced control systems for the improvement of nuclear power plant reliability and efficiency, but also provides a road map to guide interested readers to plan and execute an advanced instrumentation and control project. The subjects include: identification of needs and requirements, justification for safety and user acceptance, and the development of an engineering process. The report should be of interest to nuclear power plant staff, I and C system designers and integrators as well as regulators and researchers. Refs, figs, tabs.

Recent advances in nuclear cardiology

International Nuclear Information System (INIS)

Lee, Won Woo

2016-01-01

Nuclear cardiology is one of the major fields of nuclear medicine practice. Myocardial perfusion studies using single-photon emission computed tomography (SPECT) have played a crucial role in the management of coronary artery diseases. Positron emission tomography (PET) has also been considered an important tool for the assessment of myocardial viability and perfusion. However, the recent development of computed tomography (CT)/magnetic resonance imaging (MRI) technologies and growing concerns about the radiation exposure of patients remain serious challenges for nuclear cardiology. In response to these challenges, remarkable achievements and improvements are currently in progress in the field of myocardial perfusion imaging regarding the applicable software and hardware. Additionally, myocardial perfusion positron emission tomography (PET) is receiving increasing attention owing to its unique capability of absolute myocardial blood flow estimation. An F-18-labeled perfusion agent for PET is under clinical trial with promising interim results. The applications of F-18 fluorodeoxyglucose (FDG) and F-18 sodium fluoride (NaF) to cardiovascular diseases have revealed details on the basic pathophysiology of ischemic heart diseases. PET/MRI seems to be particularly promising for nuclear cardiology in the future. Restrictive diseases, such as cardiac sarcoidosis and amyloidosis, are effectively evaluated using a variety of nuclear imaging tools. Considering these advances, the current challenges of nuclear cardiology will become opportunities if more collaborative efforts are devoted to this exciting field of nuclear medicine

The status of nuclear fuel cycle system analysis for the development of advanced nuclear fuel cycles

Energy Technology Data Exchange (ETDEWEB)

Ko, Won Il; Kim, Seong Ki; Lee, Hyo Jik; Chang, Hong Rae; Kwon, Eun Ha; Lee, Yoon Hee; Gao, Fanxing [KAERI, Daejeon (Korea, Republic of)

2011-11-15

The system analysis has been used with different system and objectives in various fields. In the nuclear field, the system can be applied from uranium mining to spent fuel reprocessing or disposal which is called the nuclear fuel cycle. The analysis of nuclear fuel cycle can be guideline for development of advanced fuel cycle through integrating and evaluating the technologies. For this purpose, objective approach is essential and modeling and simulation can be useful. In this report, several methods which can be applicable for development of advanced nuclear fuel cycle, such as TRL, simulation and trade analysis were explained with case study

Nuclear safety research

International Nuclear Information System (INIS)

1999-01-01

The NNSA checked and coordinated in 1999 the research project of the Surveillance Technology on Nuclear Installations under the National 9th-Five-Year Program to promote the organizations that undertake the research work on schedule and lay a foundation of obtaining achievements and effectiveness for the 9th-five-year plan on nuclear safety research

Cost/Benefit Prioritization for Advanced Safeguards Research and Development

International Nuclear Information System (INIS)

DeMuth, S.F.; Adeli, R.; Thomas, K.E.

2008-01-01

A system level study utilizing commercially available Extend TM software, has been initiated to perform cost/benefit analyses for advanced safeguards research and development. The methodology is focused on estimating standard error in the inventory difference (SEID) for reprocessing and fuel fabrication facilities, for various proposed advanced safeguards measurement technologies. The inventory duration, and consequent number of inventories per year, is dictated by the detection of a significant quantity of special nuclear material (SNM). Detection is limited by the cumulative measurement uncertainty for the entire system. The cost of inventories is then compared with the cost of advanced instrumentation and/or process design changes. Current progress includes development of the methodology, future efforts will be focused on ascertaining estimated costs and performance. Case studies will be provided as examples of the methodology. (author)

Proceedings of the 2006 international congress on advances in nuclear power plants - ICAPP'06

International Nuclear Information System (INIS)

2006-01-01

Following the highly successful ICAPP'05 meeting held in Seoul Korea, the 2006 International Congress on Advances in Nuclear Power Plants brought together international experts of the nuclear industry involved in the operation, development, building, regulation and research related to Nuclear Power Plants. The program covers the full spectrum of Nuclear Power Plant issues from design, deployment and construction of plants to research and development of future designs and advanced systems. The program covers lessons learned from power, research and demonstration reactors from over 50 years of experience with operation and maintenance, structures, materials, technical specifications, human factors, system design and reliability. The program by technical track deals with: - 1. Water-Cooled Reactor Programs and Issues Evolutionary designs, innovative, passive, light and heavy water cooled reactors; issues related to meeting medium term utility needs; design and regulatory issues; business, political and economic challenges; infrastructure limitations and improved construction techniques including modularization. - 2. High Temperature Gas Cooled Reactors Design and development issues, components and materials, safety, reliability, economics, demonstration plants and environmental issues, fuel design and reliability, power conversion technology, hydrogen production and other industrial uses; advanced thermal and fast reactors. - 3. Long Term Reactor Programs and Strategies Reactor technology with enhanced fuel cycle features for improved resource utilization, waste characteristics, and power conversion capabilities. Potential reactor designs with longer development times such as, super critical water reactors, liquid metal reactors, gaseous and liquid fuel reactors, Gen IV, INPRO, EUR and other programs. - 4. Operation, Performance and Reliability Management Training, O and M costs, life cycle management, risk based maintenance, operational experiences, performance and

Advanced concepts for waste management and nuclear energy production in the EURATOM 5. framework programme

International Nuclear Information System (INIS)

Hugon, M.; Bhatnagar, V.P.; Martin Bermejon, J.

2002-01-01

This paper summarises the objectives of the research projects on partitioning and transmutation (P and T) of long-lived radionuclides in nuclear waste and advanced systems for nuclear energy production in the key action on nuclear fission of the EURATOM 5. Framework Programme (FP5) (1998-2002). As these FP5 projects cover the main aspects of P and T, they should provide a basis for evaluating the practicability, on an industrial scale, of P and T for reducing the amount of long-lived radionuclides to be disposed of. Concerning advanced concepts, a cluster of projects is addressing the key technical issues to be solved before implementing high-temperature reactors (HTRs) commercially for energy production. Finally, the European Commissions proposal fora New Framework Programme (2002-2006) is briefly outlined. (authors)

Advanced concepts for waste management and nuclear energy production in the EURATOM fifth framework programme

International Nuclear Information System (INIS)

Hugon, M.; Bhatnagar, V.P.; Martin Bermejo, J.

2001-01-01

This paper summarises the objectives of the research projects on Partitioning and Transmutation (P and T) of long lived radionuclides in nuclear waste and advanced systems for nuclear energy production in the key action on nuclear fission of the EURATOM Fifth Framework Programme (FP5) (1998-2002). As these FP5 projects cover the main aspects of P and T, they should provide a basis for evaluating the practicability, on an industrial scale, of P and T for reducing the amount of long lived radionuclides to be disposed of. Concerning advanced concepts, a cluster of projects is addressing the key technical issues to be solved before implementing High Temperature Reactors (HTRs) commercially for energy production. Finally, the European Commission(tm)s proposal for a New Framework Programme (2002-2006) is briefly outlined. (author)

A proposal for cooperative activities between Japan and Indonesia in the field of nuclear research and nuclear education

International Nuclear Information System (INIS)

Subki, Iyos

2008-01-01

Development and realization of cooperative activities between Japan and Indonesia in nuclear research and education is indeed very important for scientists and engineers of both countries. This bilateral cooperation can easily be expanded into a regional cooperation benefiting the scholars from Asian region which is expecting a New Nuclear Age in the 21st Century. To develop and realize this cooperative activities, in the first step, we invite the ideas of our partners in the Nuclear Institution and in Universities. They are eager to have and undertake this cooperation effort. For nuclear research activities, they have proposed several topics which include: advanced radioactive waste technology and management in a nuclear power plant, innovative fuel development for LWR's, gas cooled reactor for electricity and hydrogen production and a topic on design and construction of high energy accelerator. Institute of Technology - Bandung (ITB), University of Gajah Mada (UGM) and School of Nuclear Technology (STTN/BATAN) are interested in cooperative works which include: joint development of standard curriculum for M.Sc. level in response to increased activities in nuclear research and nuclear power development, exchange of guest lecturers, and exchange of M.Sc. level students. With this cooperation, we want to put very special emphasis on nuclear human resources development (nuclear - HRD) in anticipation of the upcoming nuclear era. (author)

Nuclear science research report

International Nuclear Information System (INIS)

1977-01-01

Research activities in nuclear science carried out during 1976 are summarized. Research centers around nuclear structure and the application of nuclear techniques to solid state science, materials, engineering, chemistry, biology, and medicine. Reactor and accelerator operations are reported. (E.C.B.)

Advanced nuclear reactor public opinion project

Energy Technology Data Exchange (ETDEWEB)

Benson, B.

1991-07-25

This Interim Report summarizes the findings of our first twenty in-depth interviews in the Advanced Nuclear Reactor Public Opinion Project. We interviewed 6 industry trade association officials, 3 industry attorneys, 6 environmentalists/nuclear critics, 3 state officials, and 3 independent analysts. In addition, we have had numerous shorter discussions with various individuals concerned about nuclear power. The report is organized into the four categories proposed at our April, 1991, Advisory Group meeting: safety, cost-benefit analysis, science education, and communications. Within each category, some change of focus from that of the Advisory Group has been required, to reflect the findings of our interviews. This report limits itself to describing our findings. An accompanying memo draws some tentative conclusions.

Advanced nuclear reactor public opinion project

International Nuclear Information System (INIS)

Benson, B.

1991-01-01

This Interim Report summarizes the findings of our first twenty in-depth interviews in the Advanced Nuclear Reactor Public Opinion Project. We interviewed 6 industry trade association officials, 3 industry attorneys, 6 environmentalists/nuclear critics, 3 state officials, and 3 independent analysts. In addition, we have had numerous shorter discussions with various individuals concerned about nuclear power. The report is organized into the four categories proposed at our April, 1991, Advisory Group meeting: safety, cost-benefit analysis, science education, and communications. Within each category, some change of focus from that of the Advisory Group has been required, to reflect the findings of our interviews. This report limits itself to describing our findings. An accompanying memo draws some tentative conclusions

A Study on planning of the international collaboration foundation for the Advanced Nuclear Technology Development Project

Energy Technology Data Exchange (ETDEWEB)

Chang, Moon Hee; Kim, H. R.; Kim, H. J. and others

2005-03-15

Korea has participated in the international collaboration programs for the development of future nuclear energy systems driven by the countries holding advanced nuclear technology and Korea and U.S. have cooperated in the INERI. This study aimed mainly at developing the plan for participation in the collaborative development of the Gen IV, searching the participation strategy for INERI and the INPRO, and the international cooperation in these programs. Contents and scope of the study for successful achievement are as follows; Investigation and analysis of international and domestic trends related to advanced nuclear technologies, Development of the plan for collaborative development of the Gen IV and conducting the international cooperation activities, Support for the activities related to I-NERI between Korea and U.S. and conducting the international cooperation, International cooperation activities for the INPRO. This study can be useful for planning the research plan and setting up of the strategy of integrating the results of the international collaboration and the domestic R and D results by combining the Gen IV and the domestic R and D in the field of future nuclear technology. Futhermore, this study can contribute to establishing the effective foundation and broadening the cooperation activities not only with the advanced countries for acquisition of the advanced technologies but also with the developing countries for the export of the domestic nuclear energy systems.

A Study on planning of the international collaboration foundation for the Advanced Nuclear Technology Development Project

International Nuclear Information System (INIS)

Chang, Moon Hee; Kim, H. R.; Kim, H. J. and others

2005-03-01

Korea has participated in the international collaboration programs for the development of future nuclear energy systems driven by the countries holding advanced nuclear technology and Korea and U.S. have cooperated in the INERI. This study aimed mainly at developing the plan for participation in the collaborative development of the Gen IV, searching the participation strategy for INERI and the INPRO, and the international cooperation in these programs. Contents and scope of the study for successful achievement are as follows; Investigation and analysis of international and domestic trends related to advanced nuclear technologies, Development of the plan for collaborative development of the Gen IV and conducting the international cooperation activities, Support for the activities related to I-NERI between Korea and U.S. and conducting the international cooperation, International cooperation activities for the INPRO. This study can be useful for planning the research plan and setting up of the strategy of integrating the results of the international collaboration and the domestic R and D results by combining the Gen IV and the domestic R and D in the field of future nuclear technology. Futhermore, this study can contribute to establishing the effective foundation and broadening the cooperation activities not only with the advanced countries for acquisition of the advanced technologies but also with the developing countries for the export of the domestic nuclear energy systems

Nuclear Research and Compliance

International Nuclear Information System (INIS)

Noramly Muslim

2012-01-01

In his speech, Professor Noramly stressed on any research conducted in Malaysian Nuclear Agency must be comply with the national and international regulations. This to avoid any problems in the future. Moreover, research conducted in Malaysian Nuclear Agency are based on nuclear matters that seems sensitive to the public communities. In order to attract the publics on the benefit of nuclear technologies in many applications, researcher also must aware about the regulations and must take care on their safety during their experiment and working. This to make the public feels that nuclear are not the bad things and erased the worseness of nuclear technology into public minds. This strategies can be used for Malaysia in embarking for their first nuclear power program and the public feels that nuclear power are not threatened to them and consequently, they will accept that program without any issues. (author)

Advanced ceramic materials for next-generation nuclear applications

Science.gov (United States)

Marra, John

2011-10-01

The nuclear industry is at the eye of a 'perfect storm' with fuel oil and natural gas prices near record highs, worldwide energy demands increasing at an alarming rate, and increased concerns about greenhouse gas (GHG) emissions that have caused many to look negatively at long-term use of fossil fuels. This convergence of factors has led to a growing interest in revitalization of the nuclear power industry within the United States and across the globe. Many are surprised to learn that nuclear power provides approximately 20% of the electrical power in the US and approximately 16% of the world-wide electric power. With the above factors in mind, world-wide over 130 new reactor projects are being considered with approximately 25 new permit applications in the US. Materials have long played a very important role in the nuclear industry with applications throughout the entire fuel cycle; from fuel fabrication to waste stabilization. As the international community begins to look at advanced reactor systems and fuel cycles that minimize waste and increase proliferation resistance, materials will play an even larger role. Many of the advanced reactor concepts being evaluated operate at high-temperature requiring the use of durable, heat-resistant materials. Advanced metallic and ceramic fuels are being investigated for a variety of Generation IV reactor concepts. These include the traditional TRISO-coated particles, advanced alloy fuels for 'deep-burn' applications, as well as advanced inert-matrix fuels. In order to minimize wastes and legacy materials, a number of fuel reprocessing operations are being investigated. Advanced materials continue to provide a vital contribution in 'closing the fuel cycle' by stabilization of associated low-level and high-level wastes in highly durable cements, ceramics, and glasses. Beyond this fission energy application, fusion energy will demand advanced materials capable of withstanding the extreme environments of high

Advanced ceramic materials for next-generation nuclear applications

Energy Technology Data Exchange (ETDEWEB)

Marra, John [Savannah River National Laboratory Aiken, SC 29802 (United States)

2011-10-29

The nuclear industry is at the eye of a 'perfect storm' with fuel oil and natural gas prices near record highs, worldwide energy demands increasing at an alarming rate, and increased concerns about greenhouse gas (GHG) emissions that have caused many to look negatively at long-term use of fossil fuels. This convergence of factors has led to a growing interest in revitalization of the nuclear power industry within the United States and across the globe. Many are surprised to learn that nuclear power provides approximately 20% of the electrical power in the US and approximately 16% of the world-wide electric power. With the above factors in mind, world-wide over 130 new reactor projects are being considered with approximately 25 new permit applications in the US. Materials have long played a very important role in the nuclear industry with applications throughout the entire fuel cycle; from fuel fabrication to waste stabilization. As the international community begins to look at advanced reactor systems and fuel cycles that minimize waste and increase proliferation resistance, materials will play an even larger role. Many of the advanced reactor concepts being evaluated operate at high-temperature requiring the use of durable, heat-resistant materials. Advanced metallic and ceramic fuels are being investigated for a variety of Generation IV reactor concepts. These include the traditional TRISO-coated particles, advanced alloy fuels for 'deep-burn' applications, as well as advanced inert-matrix fuels. In order to minimize wastes and legacy materials, a number of fuel reprocessing operations are being investigated. Advanced materials continue to provide a vital contribution in 'closing the fuel cycle' by stabilization of associated low-level and high-level wastes in highly durable cements, ceramics, and glasses. Beyond this fission energy application, fusion energy will demand advanced materials capable of withstanding the extreme

Experimental research progress on passive safety systems of Chinese advanced PWR

International Nuclear Information System (INIS)

Xiao Zejun; Zhuo Wenbin; Zheng Hua; Chen Bingde; Zong Guifang; Jia Dounan

2003-01-01

TMI and Chernobyl accidents, having pronounced impact on nuclear industries, triggered the governments as well as interested institutions to devote much attention to the safety of nuclear power plant and public's requirements on nuclear power plant safety were also going to be stricter and stricter. It is obvious that safety level of an ordinary light water reactor is no longer satisfactory to these requirements. Recently, the safety authorities have recommended the implementation of passive system to improve the safety of nuclear reactors. Passive safety system is one of the main differences between Chinese advanced PWR and other conventional PWR. The working principle of passive safety system is to utilize the gravity, natural convection (natural circulation) and stored energy to implement the system's safety function. Reactors with passive safety systems are not only safer, but also more economical. The passive safety system of Chinese advanced PWR is composed of three independent systems, i.e. passive containment cooling system, passive residual heat removal system and passive core makeup tank injection system. This paper is a summary of experimental research progress on passive containment cooling system, passive residual heat removal system and passive core makeup tank injection system

Structure design and realization of advanced nuclear reactor expert evaluation system

International Nuclear Information System (INIS)

Gao Bin; Zhou Zhiwei; Gu Junyang

2007-01-01

Advanced nuclear reactor expert evaluation system is the initial practice of software on nuclear power plants evaluation system. The system was developed in C++ code under the Visual Studio Net environment, and it used Model-View-Control (MVC) pattern as its basic frame. The system was used to access the advanced nuclear reactor in China. Available results illustrate that the frame of the system is feasible and effective. (authors)

Advanced applications of water cooled nuclear power plants

International Nuclear Information System (INIS)

2008-07-01

By August 2007, there were 438 nuclear power plants (NPPs) in operation worldwide, with a total capacity of 371.7 GW(e). Further, 31 units, totaling 24.1 GW(e), were under construction. During 2006 nuclear power produced 2659.7 billion kWh of electricity, which was 15.2% of the world's total. The vast majority of these plants use water-cooled reactors. Based on information provided by its Member States, the IAEA projects that nuclear power will grow significantly, producing between 2760 and 2810 billion kWh annually by 2010, between 3120 and 3840 billion kWh annually by 2020, and between 3325 and 5040 billion kWh annually by 2030. There are several reasons for these rising expectations for nuclear power: - Nuclear power's lengthening experience and good performance: The industry now has more than 12 000 reactor years of experience, and the global average nuclear plant availability during 2006 reached 83%; - Growing energy needs: All forecasts project increases in world energy demand, especially as population and economic productivity grow. The strategies are country dependent, but usually involve a mix of energy sources; - Interest in advanced applications of nuclear energy, such as seawater desalination, steam for heavy oil recovery and heat and electricity for hydrogen production; - Environmental concerns and constraints: The Kyoto Protocol has been in force since February 2005, and for many countries (most OECD countries, the Russian Federation, the Baltics and some countries of the Former Soviet Union and Eastern Europe) greenhouse gas emission limits are imposed; - Security of energy supply is a national priority in essentially every country; and - Nuclear power is economically competitive and provides stability of electricity price. In the near term most new nuclear plants will be evolutionary water cooled reactors (Light Water Reactors (LWRs) and Heavy Water Reactors (HWRs), often pursuing economies of scale. In the longer term, innovative designs that

Institute for Nuclear Research and Nuclear Energy and Nuclear Science

International Nuclear Information System (INIS)

Stamenov, J.

2004-01-01

The Institute for Nuclear Research and Nuclear Energy (INRNE) of the Bulgarian Academy of Sciences is the leading Bulgarian Institute for scientific investigations and applications of nuclear science. The main Institute's activities in the field of elementary particles and nuclear physics, high energy physics and nuclear energy, radiochemistry, radioecology, radioactive wastes treatment, monitoring of the environment, nuclear instruments development ect. are briefly described. Several examples for: environmental radiation monitoring; monitoring of the radioactivity and heavy metals in aerosols, 99m Tc clinical use, Boron Neutron Capture Therapy application of IRT-2000 Research Reactor, neutron fluence for reactor vessel embrittlement, NPP safety analysis, nuclear fuel modelling are also presented

Advanced nuclear fuel cycles activities in IAEA

International Nuclear Information System (INIS)

Nawada, H.P.; Ganguly, C.

2007-01-01

Full text of publication follows. Of late several developments in reprocessing areas along with advances in fuel design and robotics have led to immense interest in partitioning and transmutation (P and T). The R and D efforts in the P and T area are being paid increased attention as potential answers to ever-growing issues threatening sustainability, environmental protection and non-proliferation. Any fuel cycle studies that integrate partitioning and transmutation are also known as ''advanced fuel cycles'' (AFC), that could incinerate plutonium and minor actinide (MA) elements (namely Am, Np, Cm, etc.) which are the main contributors to long-term radiotoxicity. The R and D efforts in developing these innovative fuel cycles as well as reactors are being co-ordinated by international initiatives such as Innovative Nuclear Power Reactors and Fuel Cycles (INPRO), the Generation IV International Forum (GIF) and the Global Nuclear Energy Partnership (GENP). For these advanced nuclear fuel cycle schemes to take shape, the development of liquid-metal-cooled reactor fuel cycles would be the most essential step for implementation of P and T. Some member states are also evaluating other concepts involving the use of thorium fuel cycle or inert-matrix fuel or coated particle fuel. Advanced fuel cycle involving novel partitioning methods such as pyrochemical separation methods to recover the transuranic elements are being developed by some member states which would form a critical stage of P and T. However, methods that can achieve a very high reduction (>99.5%) of MA and long-lived fission products in the waste streams after partitioning must be achieved to realize the goal of an improved protection of the environment. In addition, the development of MA-based fuel is also an essential and crucial step for transmutation of these transuranic elements. The presentation intends to describe progress of the IAEA activities encompassing the following subject-areas: minimization of

Development of a 1200 fine group nuclear data library for advanced nuclear systems

Institute of Scientific and Technical Information of China (English)

Jun Zou; Lei-Ming Shang; Fang Wang; Li-Juan Hao

2017-01-01

Accurate and reliable nuclear data libraries are essential for calculation and design of advanced nuclear systems.A 1200 fine group nuclear data library Hybrid Evaluated Nuclear Data Library/Fine Group (HENDL/FG) with neutrons of up to 150 MeV has been developed to improve the accuracy of neutronics calculations and analysis.Corrections of Doppler,resonance self-shielding,and thermal upscatter effects were done for HENDL/FG.Shielding and critical safety benchmarks were performed to test the accuracy and reliability of the library.The discrepancy between calculated and measured nuclear parameters fell into a reasonable range.

Advances in nuclear science and technology

CERN Document Server

Henley, Ernest J

1975-01-01

Advances in Nuclear Science and Technology, Volume 8 discusses the development of nuclear power in several countries throughout the world. This book discusses the world's largest program of land-based electricity production in the United States.Organized into six chapters, this volume begins with an overview of the phenomenon of quasi-exponential behavior by examining two mathematical models of the neutron field. This text then discusses the finite element method, which is a method for obtaining approximate solutions to integral or differential equations. Other chapters consider the status of

Radioactive waste management and advanced nuclear fuel cycle technologies

International Nuclear Information System (INIS)

2007-01-01

In 2007 ENEA's Department of Nuclear Fusion and Fission, and Related Technologies acted according to national policy and the role assigned to ENEA FPN by Law 257/2003 regarding radioactive waste management and advanced nuclear fuel cycle technologies

US Department of Energy Nuclear Research and Development Program

International Nuclear Information System (INIS)

Griffith, J.D.

1989-01-01

The presentation includes a discussion of nuclear power in the United States with respect to public opinion, energy consumption, economics, technology, and safety. The focus of the presentation is the advanced light water reactor strategy, liquid metal cooled reactor program, the modular high temperature gas cooled reactor program, and DOE research and test reactor facilities utilization. The discussion includes programmatic status and planning

Advanced nuclear systems. Review study; Fortgeschrittene Nuklearsysteme. Review Study

Energy Technology Data Exchange (ETDEWEB)

Liebert, Wolfgang; Glaser, Alexander; Pistner, Christoph [Interdisziplinaere Arbeitsgruppe Naturwissenschaft, Technik und Sicherheit (IANUS), Darmstadt University of Technology, Hochschulstrasse 10, D-64289 Darmstadt (Germany); Baehr, Roland; Hahn, Lothar [Institute for applied ecology (Oeko-Institut), Elisabethenstrasse 55-57, D-64283 Darmstadt (Germany)

1999-04-01

The task of this review study is to from provide an overview of the developments in the field of the various advanced nuclear systems, and to create the basis for more comprehensive studies of technology assessment. In an overview the concepts for advanced nuclear systems pursued worldwide are subdivided into eight subgroups. A coarse examination raster (set pattern) is developed to enable a detailed examination of the selected systems. In addition to a focus on enhanced safety features, further aspects are also taken into consideration, like the lowering of the proliferation risk, the enhancement of the economic competitiveness of the facilities and new usage possibilities (for instance concerning the relaxation of the waste disposal problem or the usage of alternative fuels to uranium). The question about the expected time span for realization and the discussion about the obstacles on the way to a commercially usable reactor also play a substantial role as well as disposal requirements as far as they can be presently recognized. In the central chapter of this study, the documentation of the representatively selected concepts is evaluated as well as existing technology assessment studies and expert opinions. In a few cases where this appears to be necessary, according technical literature, further policy advisory reports, expert statements as well as other relevant sources are taken into account. Contradictions, different assessments and dissents in the literature as well as a few unsettled questions are thus indicated. The potential of advanced nuclear systems with respect to economical and societal as well as environmental objectives cannot exclusively be measured by the corresponding intrinsic or in comparison remarkable technical improvements. The acceptability of novel or improved systems in nuclear technology will have to be judged by their convincing solutions for the crucial questions of safety, nuclear waste and risk of proliferation of nuclear weapons

Advanced nuclear energy systems and the need of accurate nuclear data: the n_TOF project at CERN

CERN Document Server

Colonna, N; Praena, J; Lederer, C; Karadimos, D; Sarmento, R; Domingo-Pardo, C; Plag, R; Massimi, C; Calviani, M; Guerrero, C; Paradela, C; Belloni, F

2010-01-01

To satisfy the world's constantly increasing demand for energy, a suitable mix of different energy sources has to be devised. In this scenario, an important role could be played by nuclear energy, provided that major safety, waste and proliferation issues affecting current nuclear reactors are satisfactorily addressed. To this purpose, a large effort has been under way for a few years towards the development of advanced nuclear systems with the aim of closing the fuel cycle. Generation IV reactors, with full or partial waste recycling capability, accelerator driven systems, as well as new fuel cycles are the main options being investigated. The design of advanced systems requires improvements in basic nuclear data, such as cross-sections for neutron-induced reactions on actinides. In this paper, the main concepts of advanced reactor systems are described, together with the related needs of new and accurate nuclear data. The present activity in this field at the neutron facility n\\_TOF at CERN is discussed.

NRC research on the application of advanced I and C technology to commercial nuclear power plants

International Nuclear Information System (INIS)

Gollei, K.R.; Hon, A.L.

1983-01-01

The operational safety and efficiency of commercial nuclear power plants (NPP's) could possibly be enhanced by utilizing advanced instrumentation and control technology developed by other industries. The NRC is interested in learning about new I and C technology that probably will or could be applied to new or existing plants. This would enable the NRC to be better prepared to evaluate the application without undue delays. It would also help identify any appropriate changes in NRC regulations or guidance necessary to facilitate the application of advanced IandC technology to NPP's. The NRC has initiated a project to work cooperatively with the advanced technology industry, power industry, EPRI, and technical organizations such as ISA toward this goal. This paper describes the objectives and plans of this cooperative effort. It summarizes the highlights of some of the advanced technology already being evaluated by NRC such as microprocessor applications, instruments to detect inadequate core cooling and other two-phase flow measurements, reactor noise surveillance and diagnostic techniques. This paper also suggests potential candidates for consideration such as utilization of advanced instruments for LOCA experiments. It also identifies some of the potential challenges facing the application of advanced technology to NPP's. It concludes that close cooperation between NRC and industry is essential for the success of such applications

Office of Nuclear Regulatory Research summary of advanced reactors activities, June 4, 2001

International Nuclear Information System (INIS)

2001-01-01

Pre-application interactions with potential licensee applicants will help NRC prepare for future submittals, through the development of the infrastructure necessary for licensing application reviews. RES has the lead for non-LWR advanced reactor pre-application initiatives and longer-range new technology initiatives. An advanced reactor group has been formed in REAHFB, and is currently performing a pre-application review of Exelon's Pebble Bed Modular Reactor. Recent industry requests for future pre application interaction include General Atomics' Gas Turbine-Modular Helium Reactor (GT-MHR) and Westinghouse International Reactor Innovative and Secure (IRIS) design. RES advanced reactors activities also include participation as an observer in DOE's Generation IV initiative. Pre-Application review objectives include the development of regulatory guidance, licensing approach, and technology-basis expectations for licensing advanced designs, including identifying significant technology, design, safety, licensing and policy issues that would need to be addressed in the licensing process. The presentation described the pre-application process for the Exelon PBMR. NRC first identifies additional information following topical meetings with Exelon, and Exelon formally documents and submits required topical Information. The staff then develops a preliminary assessment and drafts a response which is followed by stakeholder input and comments at a public workshop. Preliminary assessments are discussed with ACRS and ACNW, and Commission papers are written which provide staff positions and recommendations on proposed policy decisions. Some of the significant areas for the PBMR include: Process Issues, Legal and Financial Issues; Regulatory Framework; Fuel Performance and Qualification; Traditional Engineering Design (e.g, Nuclear, Thermal-Fluid, Materials); Fuel Cycle Safety Areas; PRA, SSC Safety Classification; PBMR Prototype Testing

Advanced research technology transfer

International Nuclear Information System (INIS)

Naraghi, Masud

1977-01-01

The importance of advanced research in the less developed countries of the world is described. Advanced research is a way of building from the top; it helps industrial development; it provides ''know-how'' economically; it enhances international understanding; it prevents the brain drain to developed countries and is of mutual benefit. The problems concerned with this type of research are pointed out

Training Activities to Maintain Competences in Nuclear Safety and Security: A Case Study of the Belgian Nuclear Research Centre

International Nuclear Information System (INIS)

Kesteloot, N.; Clarijs, T.; Coeck, M.; Vermeersch, F.

2016-01-01

Full text: The Belgian Nuclear Research Centre, SCK•CEN, is one of the largest research centers in Belgium. More than 700 employees advance research into nuclear energy and ionizing radiation for civilian use, and develop nuclear technologies for socially valuable purposes. Next to independent fundamental and applied research SCK-CEN provides advice, training, services and products. This paper describes the general approach towards the continuous professional development of all SCK-CEN personnel. The objective of these training activities is to maintain and increase the required competences, in order to optimize the output and the wellbeing on the work floor. Given the nature of the SCK-CEN activities, special attention is given to themes like radiation protection, security and industrial safety. A combination of classical face-to-face training, e-learning and on-the-job training is offered during the onboarding and further career path of an SCK-CEN employee. (author

Advancement on safety management system of nuclear power for safety and non-anxiety of society

International Nuclear Information System (INIS)

Yoshikawa, Hidekazu

2004-01-01

Advancement on safety management system is investigated to improve safety and non-anxiety of society for nuclear power, from the standpoint of human machine system research. First, the recent progress of R and D works of human machine interface technologies since 1980 s are reviewed and then the necessity of introducing a new approach to promote technical risk communication activity to foster safety culture in nuclear industries. Finally, a new concept of Offsite Operation and Maintenance Support Center (OMSC) is proposed as the core facility to assemble human resources and their expertise in all organizations of nuclear power, for enhancing safety and non-anxiety of society for nuclear power. (author)

Potential human factors research relating to modern technology in nuclear power plants

International Nuclear Information System (INIS)

Ketchel, J.; Fink, R.; Hanes, L.; Williges, R.; Williges, B.

1994-01-01

This paper discusses proposed human factors research to address advanced human-machine interface technology in nuclear power plants. It relates to a current EPRI project to identify a prioritized list of specific research issues that could be assessed to improve control room and other user interface areas. The project seeks to bridge the gap between the functional requirements of advanced design initiatives and the human factors research needed to support them. It seeks to identify potential benefits to be expected, as well as potential problems that might be introduced by advanced technology. It provides an organized approach to identifying human factors research needs, information already available, and measures of performance and effectiveness that might be used to assess the value of potential improvements. Those parts of the proposed plan that are subsequently approved by EPRI management and by the utility advisory committee will provide a basis for recommending research priorities

The advanced fuel cycle facility (AFCF) role in the global nuclear energy partnership

International Nuclear Information System (INIS)

Griffith, Andrew

2007-01-01

The Global Nuclear Energy Partnership (GNEP), launched in February, 2006, proposes to introduce used nuclear fuel recycling in the United States with improved proliferation-resistance and a more effective waste management approach. This program is evaluating ways to close the fuel cycle in a manner that builds on recent laboratory breakthroughs in U.S. national laboratories and draws on international and industry partnerships. Central to moving this advanced fuel recycling technology from the laboratory to commercial implementation is a flexible research, development and demonstration facility, called the Advanced Fuel Cycle Facility (AFCF). The AFCF was introduced as one of three projects under GNEP and will provide the U.S. with the capabilities to evaluate technologies that separate used fuel into reusable material and waste in a proliferation-resistant manner. The separations technology demonstration capability is coupled with a remote transmutation fuel fabrication demonstration capability in an integrated manner that demonstrates advanced safeguard technologies. This paper will discuss the key features of AFCF and its support of the GNEP objectives. (author)

High Level Requirements for the Nuclear Energy -- Knowledge Base for Advanced Modeling and Simulation (NE-KAMS)

Energy Technology Data Exchange (ETDEWEB)

Rich Johnson; Hyung Lee; Kimberlyn C. Mousseau

2011-09-01

The US Department of Energy, Office of Nuclear Energy (DOE-NE), has been tasked with the important mission of ensuring that nuclear energy remains a compelling and viable energy source in the U.S. The motivations behind this mission include cost-effectively meeting the expected increases in the power needs of the country, reducing carbon emissions and reducing dependence on foreign energy sources. In the near term, to ensure that nuclear power remains a key element of U.S. energy strategy and portfolio, the DOE-NE will be working with the nuclear industry to support safe and efficient operations of existing nuclear power plants. In the long term, to meet the increasing energy needs of the U.S., the DOE-NE will be investing in research and development (R&D) and working in concert with the nuclear industry to build and deploy new, safer and more efficient nuclear power plants. The safe and efficient operations of existing nuclear power plants and designing, licensing and deploying new reactor designs, however, will require focused R&D programs as well as the extensive use and leveraging of advanced modeling and simulation (M&S). M&S will play a key role in ensuring safe and efficient operations of existing and new nuclear reactors. The DOE-NE has been actively developing and promoting the use of advanced M&S in reactor design and analysis through its R&D programs, e.g., the Nuclear Energy Advanced Modeling and Simulation (NEAMS) and Consortium for Advanced Simulation of Light Water Reactors (CASL) programs. Also, nuclear reactor vendors are already using CFD and CSM, for design, analysis, and licensing. However, these M&S tools cannot be used with confidence for nuclear reactor applications unless accompanied and supported by verification and validation (V&V) and uncertainty quantification (UQ) processes and procedures which provide quantitative measures of uncertainty for specific applications. The Nuclear Energy Knowledge base for Advanced Modeling and Simulation

Nuclear techniques in the development of advanced ceramic technologies

International Nuclear Information System (INIS)

Axe, J.D.; Hewat, A.W.; Maier, J.; Margaca, F.M.A.; Rauch, H.

1999-01-01

The importance of research, development and application of advanced materials is well understood by all developed and most developing countries. Amongst advanced materials, ceramics play a prominent role due to their specific chemical and physical properties. According to performance and importance, advanced ceramics can be classified as structural ceramics (mechanical function) and the so-called functional ceramics. In the latter class of materials, special electrical, chemical, thermal, magnetic and optical properties are of interest. The most valuable materials are multifunctional, for example, when structural ceramics combine beneficial mechanical properties with thermal and chemical sensitivity. Multifunctionality is characteristic of many composite materials (organic/inorganic composite). Additionally, properties of material can be changed by reducing its dimension (thin films, nanocrystalline ceramics). Nuclear techniques, found important applications in research and development of advanced ceramics. The use of neutron techniques has increased dramatically in recent years due to the development of advanced neutron sources, instrumentation and improved data analysis. Typical neutron techniques are neutron diffraction, neutron radiography, small angle neutron scattering and very small angle neutron scattering. Neutrons can penetrate deeply into most materials thus sampling their bulk properties. In determination of the crystal structure of HTSC, YBa 2 Cu 2 O 7 , XRD located the heavy metal atoms, but failed in finding many of the oxygen atoms, while the neutron diffraction located all atoms equally well in the crystal structure. Neutron diffraction is also unique for the determination of the magnetic structure of materials since the neutrons themselves have a magnetic moment. Application of small angle neutron scattering for the determination of the size of hydrocarbon aggregates within the zeolite channels is illustrated. (author)

Nuclear energy related research

International Nuclear Information System (INIS)

Rintamaa, R.

1992-05-01

The annual Research Programme Plan describes publicly funded nuclear energy related research to be carried out mainly at the Technical Research Centre of Finland (VTT) in 1992. The research is financed primarily by the Ministry of Trade and Industry (KTM), the Finnish Centre for Radiation and Nuclear Safety (STUK) and VTT itself. Other research institutes, utilities and industry also contribute to many projects

Advanced construction methods for new nuclear power plants

International Nuclear Information System (INIS)

Bilbao y Leon, Sama; Cleveland, John; Moon, Seong-Gyun; Tyobeka, Bismark

2009-01-01

The length of the construction and commissioning phases of nuclear power plants have historically been longer than for conventional fossil fuelled plants, often having a record of delays and cost overruns as a result from several factors including legal interventions and revisions of safety regulations. Recent nuclear construction projects however, have shown that long construction periods for nuclear power plants are no longer the norm. While there are several inter-related factors that influence the construction time, the use of advanced construction techniques has contributed significantly to reducing the construction length of recent nuclear projects. (author)

Science based integrated approach to advanced nuclear fuel development - vision, approach, and overview

Energy Technology Data Exchange (ETDEWEB)

Unal, Cetin [Los Alamos National Laboratory; Pasamehmetoglu, Kemal [IDAHO NATIONAL LAB; Carmack, Jon [IDAHO NATIONAL LAB

2010-01-01

Advancing the performance of Light Water Reactors, Advanced Nuclear Fuel Cycles, and Advanced Rcactors, such as the Next Generation Nuclear Power Plants, requires enhancing our fundamental understanding of fuel and materials behavior under irradiation. The capability to accurately model the nuclear fuel systems is critical. In order to understand specific aspects of the nuclear fuel, fully coupled fuel simulation codes are required to achieve licensing of specific nuclear fuel designs for operation. The backbone of these codes, models, and simulations is a fundamental understanding and predictive capability for simulating the phase and microstructural behavior of the nuclear fuel system materials and matrices. The purpose of this paper is to identify the modeling and simulation approach in order to deliver predictive tools for advanced fuels development. The coordination between experimental nuclear fuel design, development technical experts, and computational fuel modeling and simulation technical experts is a critical aspect of the approach and naturally leads to an integrated, goal-oriented science-based R & D approach and strengthens both the experimental and computational efforts. The Advanced Fuels Campaign (AFC) and Nuclear Energy Advanced Modeling and Simulation (NEAMS) Fuels Integrated Performance and Safety Code (IPSC) are working together to determine experimental data and modeling needs. The primary objective of the NEAMS fuels IPSC project is to deliver a coupled, three-dimensional, predictive computational platform for modeling the fabrication and both normal and abnormal operation of nuclear fuel pins and assemblies, applicable to both existing and future reactor fuel designs. The science based program is pursuing the development of an integrated multi-scale and multi-physics modeling and simulation platform for nuclear fuels. This overview paper discusses the vision, goals and approaches how to develop and implement the new approach.

Science based integrated approach to advanced nuclear fuel development - vision, approach, and overview

International Nuclear Information System (INIS)

Unal, Cetin; Pasamehmetoglu, Kemal; Carmack, Jon

2010-01-01

Advancing the performance of Light Water Reactors, Advanced Nuclear Fuel Cycles, and Advanced Rcactors, such as the Next Generation Nuclear Power Plants, requires enhancing our fundamental understanding of fuel and materials behavior under irradiation. The capability to accurately model the nuclear fuel systems is critical. In order to understand specific aspects of the nuclear fuel, fully coupled fuel simulation codes are required to achieve licensing of specific nuclear fuel designs for operation. The backbone of these codes, models, and simulations is a fundamental understanding and predictive capability for simulating the phase and microstructural behavior of the nuclear fuel system materials and matrices. The purpose of this paper is to identify the modeling and simulation approach in order to deliver predictive tools for advanced fuels development. The coordination between experimental nuclear fuel design, development technical experts, and computational fuel modeling and simulation technical experts is a critical aspect of the approach and naturally leads to an integrated, goal-oriented science-based R and D approach and strengthens both the experimental and computational efforts. The Advanced Fuels Campaign (AFC) and Nuclear Energy Advanced Modeling and Simulation (NEAMS) Fuels Integrated Performance and Safety Code (IPSC) are working together to determine experimental data and modeling needs. The primary objective of the NEAMS fuels IPSC project is to deliver a coupled, three-dimensional, predictive computational platform for modeling the fabrication and both normal and abnormal operation of nuclear fuel pins and assemblies, applicable to both existing and future reactor fuel designs. The science based program is pursuing the development of an integrated multi-scale and multi-physics modeling and simulation platform for nuclear fuels. This overview paper discusses the vision, goals and approaches how to develop and implement the new approach.

Position paper on main areas of nuclear chemistry research and application

International Nuclear Information System (INIS)

2001-01-01

Nuclear chemistry, with its specialized areas of nuclear chemistry, radiochemistry, and radiation chemistry, mainly covers these fields: basic research in nuclear chemistry; actinide chemistry; radioanalysis; nuclear chemistry in the life sciences, geosciences, and cosmic chemistry; radiotracers in technology; nuclear power technology; nuclear waste management; tritium chemistry in fusion technology, and radiation protection and radioecology. In the more than one hundred years of history of this branch of science and technology, which was opened up by the discovery of radioactivity and of the radioelements, pioneering discoveries and developments have been made in many sectors. Far beyond the confines of this area of work, they have achieved overriding importance in applications in many fields of technology and industry and in the life sciences. Research and application in nuclear chemistry continue to be highly relevant to society, ecology, and the economy, and the potential of science and technology in this field in Germany is acknowledged internationally. In the light of this vast area of activity, and against the need to maintain competence in nuclear chemistry for the use of nuclear power, irrespective of the status of this continued use in Germany, nuclear chemistry is indispensable to the solution of future problems. The Nuclear Chemistry Group of the Gesellschaft Deutscher Chemiker therefore uses this position paper to draw attention to the urgent need to keep up and further advance nuclear chemistry applications in a variety of areas of science and technology, also as a public duty of thorough education and research. (orig.) [de

Proceedings of the second international conference on advances in nuclear materials: abstract booklet and souvenir

International Nuclear Information System (INIS)

2011-01-01

Nuclear materials form special class of materials which either act as fuel for the nuclear reactors or form the structure of the reactors and the allied systems. The topics covered in this conference are: materials challenges for thermal and fast reactors, technological advances in nuclear fuels and components, materials for future reactors, fuel cycles and materials challenges, materials degradation and life management, advanced materials development, modelling and simulation, advanced materials- II, advanced materials for future reactors, development of advanced fuel and structural materials, zirconium alloy developments, irradiation effects and PIE, advanced nuclear fuels, corrosion and materials characterization. Papers relevant to INIS are indexed separately

Construction and engineering report for advanced nuclear fuel development facility

International Nuclear Information System (INIS)

Cho, S. W.; Park, J. S.; Kwon, S.J.; Lee, K. W.; Kim, I. J.; Yu, C. H.

2003-09-01

The design and construction of the fuel technology development facility was aimed to accommodate general nuclear fuel research and development for the HANARO fuel fabrication and advanced fuel researches. 1. Building size and room function 1) Building total area : approx. 3,618m 2 , basement 1st floor, ground 3th floor 2) Room function : basement floor(machine room, electrical room, radioactive waste tank room), 1st floor(research reactor fuel fabrication facility, pyroprocess lab., metal fuel lab., nondestructive lab., pellet processing lab., access control room, sintering lab., etc), 2nd floor(thermal properties measurement lab., pellet characterization lab., powder analysis lab., microstructure analysis lab., etc), 3rd floor(AHU and ACU Room) 2. Special facility equipment 1) Environmental pollution protection equipment : ACU(2sets), 2) Emergency operating system : diesel generator(1set), 3) Nuclear material handle, storage and transport system : overhead crane(3sets), monorail hoist(1set), jib crane(2sets), tank(1set) 4) Air conditioning unit facility : AHU(3sets), packaged air conditioning unit(5sets), 5) Automatic control system and fire protection system : central control equipment(1set), lon device(1set), fire hose cabinet(3sets), fire pump(3sets) etc

Nuclear energy related research

International Nuclear Information System (INIS)

Salminen, Pertti

1989-03-01

This annual Research Programme Plan covers the publicly funded nuclear energy related research planned to be carried out at the Technical Research Centre of Finland (VTT) in 1989. The research will be financed by the Ministry of Trade and Industry, the Finnish Centre for Radiation and Nuclear Safety, the Nordic Council of Ministers and VTT itself

Nuclear energy related research

International Nuclear Information System (INIS)

Salminen, P.

1988-02-01

This annual Research Programme Plan covers the publicly funded nuclear energy related research planned to be carried out at the Technical Research Centre of Finland (VTT) in 1988. The research will be financed by the Ministry of Trade and Industry, the Finnish Centre for Radiation and Nuclear Safety, the Nordic Council of Ministers and VTT itself

Advanced Reactor Technology Options for Utilization and Transmutation of Actinides in Spent Nuclear Fuel

International Nuclear Information System (INIS)

2009-09-01

Renewed interest in the potential of nuclear energy to contribute to a sustainable worldwide energy mix is strengthening the IAEA's statutory role in fostering the peaceful uses of nuclear energy, in particular the need for effective exchanges of information and collaborative research and technology development among Member States on advanced nuclear power technologies (Articles III-A.1 and III-A.3). The major challenges facing the long term development of nuclear energy as a part of the world's energy mix are improvement of the economic competitiveness, meeting increasingly stringent safety requirements, adhering to the criteria of sustainable development, and public acceptability. The concern linked to the long life of many of the radioisotopes generated from fission has led to increased R and D efforts to develop a technology aimed at reducing the amount of long lived radioactive waste through transmutation in fission reactors or accelerator driven hybrids. In recent years, in various countries and at an international level, more and more studies have been carried out on advanced and innovative waste management strategies (i.e. actinide separation and elimination). Within the framework of the Project on Technology Advances in Fast Reactors and Accelerator Driven Systems (http://www.iaea.org/inisnkm/nkm/aws/fnss/index.html), the IAEA initiated a number of activities on utilization of plutonium and transmutation of long lived radioactive waste, accelerator driven systems, thorium fuel options, innovative nuclear reactors and fuel cycles, non-conventional nuclear energy systems, and fusion/fission hybrids. These activities are implemented under the guidance and with the support of the IAEA Nuclear Energy Department's Technical Working Group on Fast Reactors (TWG-FR). This publication compiles the analyses and findings of the Coordinated Research Project (CRP) on Studies of Advanced Reactor Technology Options for Effective Incineration of Radioactive Waste (2002

Holistic safety analysis for advanced nuclear power plants

International Nuclear Information System (INIS)

Alvarenga, M.A.B.; Guimaraes, A.C.F.

1992-01-01

This paper reviews the basic methodology of safety analysis used in the ANGRA-I and ANGRA-II nuclear power plants, its weaknesses, the problems with public acceptance of the risks, the future of the nuclear energy in Brazil, as well as recommends a new methodology, HOLISTIC SAFETY ANALYSIS, to be used both in the design and licensing phases, for advanced reactors. (author)

Nuclear energy related research

International Nuclear Information System (INIS)

Mattila, L.; Vanttola, T.

1991-10-01

The annual Research Programme Plan describes the publicly funded nuclear energy related research to be carried out mainly at the Technical Research Centre of Finland (VTT) in 1991. The research is financed primarily by the Ministry of Trade and Industry (KTM), the Finnish Centre for Radiation and Nuclear Safety (STUK) and VTT itself. Other research institutes, utilities and industry also contribute to many projects

Nuclear research centres in the 21st century: The French perspective

International Nuclear Information System (INIS)

Graviere, M. de la

2001-01-01

In France the reactor technology is mature and R and D needs for reactors are small. However, there are substantial R and D needs in the electro-nuclear field. These include optimization of operation of nuclear power plants and the associated factories and to have a long term vision for the nuclear technologies. The State continues to be a major provider of resources for the long term strategic objectives. However, lack of resources has resulted in shutting down of some large facilities and it is becoming difficult to refurbish some large experimental tools. The possibility of earning resources through solving complex problems beyond the nuclear field is, therefore, under exploration. Nuclear research centres are also looking into new advanced technologies (energy, micro electronics, materials, bio-technology) and for development of partnership with other public research organisations. The issue of preservation of expertise is being addressed by development of networks between the European centres working in the same field. Cost and risk sharing of nuclear R and D is being pursued by collaboration with countries outside Europe, namely the USA, Japan and China. Public perception of nuclear energy is being enhanced by opening CEA centres to the public. (author)

Advanced Nuclear Fuels Corporation: one year later

International Nuclear Information System (INIS)

Bjoernard, T.A.; Sofer, G.A.

1988-01-01

About one year ago, after 18 years of business as a wholly owned affiliate of Exxon Corporation, Exxon Nuclear Company was acquired by Siemens/KWU and its name was changed to Advanced Nuclear Fuels Corporation (ANF). This profile describes the status of ANF one year later, principally from the European perspective but with some mention of ANF's worldwide operations to provide a balanced picture. After one year of operation as an affiliate of Siemens/KWU, ANF's role remains as an independent international supplier of nuclear fuel and services to utilities in Europe, the USA and the Far East, but with substantially augmented capabilities resulting from the new affiliation

The Westinghouse AP600 an advanced nuclear option for small or medium electricity grids

International Nuclear Information System (INIS)

Bruschi, H. J.; Novak, V.

1996-01-01

During the early days of commercial nuclear power, many countries looking to add nuclear power to their energy mix required large plants to meet the energy needs of rapidly growing populations and large industrial complexes. The majority of plants worldwide are in the range of 100 megawatts and beyond. During the 1970s, it became apparent that a smaller nuclear plants would appeal to utilities looking to add additional power capacity to existing grids, or to utilities in smaller countries which were seeking efficient, new nuclear generation capacity for the first time. For instance, the Westinghouse-designed 600 megawatt Krsko plant in Slovenia began operation in 1980, providing electricity to inhabitants of relatively small, yet industrial populations of Slovenia and Croatia. This plant design incorporated the best, proven technology available at that time, based on 20 years of Westinghouse PWR pioneering experience. Beginning in the early 1980s, Westinghouse began to build further upon that experience - in part through the advanced light water reactor programs established by the Electric Power Research institute (EPRI) and the U.S. Department of Energy (DOE) - to design a simplified, advanced nuclear reactor in the 600 megawatt range. Originally, Westinghouse's development of its AP600 (advanced, passive 600-megawatt) plants was geared towards the needs of U.S. utilities which specified smaller, simplified nuclear options for the decades ahead. It soon became evident that the small and medium sized electricity grids of international markets could benefit from this new reactor. From the earliest days of Westinghouse's AP600 development, the corporation invited members of the international nuclear community to take part in the design, development and testing of the AP600 - with the goal of designing a reactor that would meet the diverse needs of an international industry composed of countries with similar, yet different, concerns. (author)

Nuclear research reactors in Brazil

Energy Technology Data Exchange (ETDEWEB)

Cota, Anna Paula Leite; Mesquita, Amir Zacarias, E-mail: aplc@cdtn.b, E-mail: amir@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2011-07-01

The rising concerns about global warming and energy security have spurred a revival of interest in nuclear energy, giving birth to a 'nuclear power renaissance' in several countries in the world. Particularly in Brazil, in the recent years, the nuclear power renaissance can be seen in the actions that comprise its nuclear program, summarily the increase of the investments in nuclear research institutes and the government target to design and build the Brazilian Multipurpose research Reactor (BMR). In the last 50 years, Brazilian research reactors have been used for training, for producing radioisotopes to meet demands in industry and nuclear medicine, for miscellaneous irradiation services and for academic research. Moreover, the research reactors are used as laboratories to develop technologies in power reactors, which are evaluated today at around 450 worldwide. In this application, those reactors become more viable in relation to power reactors by the lowest cost, by the operation at low temperatures and, furthermore, by lower demand for nuclear fuel. In Brazil, four research reactors were installed: the IEA-R1 and the MB-01 reactors, both at the Instituto de Pesquisas Energeticas Nucleares (IPEN, Sao Paulo); the Argonauta, at the Instituto de Engenharia Nuclear (IEN, Rio de Janeiro) and the IPR-R1 TRIGA reactor, at the Centro de Desenvolvimento da Tecnologia Nuclear (CDTN, Belo Horizonte). The present paper intends to enumerate the characteristics of these reactors, their utilization and current academic research. Therefore, through this paper, we intend to collaborate on the BMR project. (author)

Nuclear research reactors in Brazil

International Nuclear Information System (INIS)

Cota, Anna Paula Leite; Mesquita, Amir Zacarias

2011-01-01

The rising concerns about global warming and energy security have spurred a revival of interest in nuclear energy, giving birth to a 'nuclear power renaissance' in several countries in the world. Particularly in Brazil, in the recent years, the nuclear power renaissance can be seen in the actions that comprise its nuclear program, summarily the increase of the investments in nuclear research institutes and the government target to design and build the Brazilian Multipurpose research Reactor (BMR). In the last 50 years, Brazilian research reactors have been used for training, for producing radioisotopes to meet demands in industry and nuclear medicine, for miscellaneous irradiation services and for academic research. Moreover, the research reactors are used as laboratories to develop technologies in power reactors, which are evaluated today at around 450 worldwide. In this application, those reactors become more viable in relation to power reactors by the lowest cost, by the operation at low temperatures and, furthermore, by lower demand for nuclear fuel. In Brazil, four research reactors were installed: the IEA-R1 and the MB-01 reactors, both at the Instituto de Pesquisas Energeticas Nucleares (IPEN, Sao Paulo); the Argonauta, at the Instituto de Engenharia Nuclear (IEN, Rio de Janeiro) and the IPR-R1 TRIGA reactor, at the Centro de Desenvolvimento da Tecnologia Nuclear (CDTN, Belo Horizonte). The present paper intends to enumerate the characteristics of these reactors, their utilization and current academic research. Therefore, through this paper, we intend to collaborate on the BMR project. (author)

Nuclear safety research in HGF 2011

International Nuclear Information System (INIS)

Tromm, Walter

2012-01-01

After the events at the Japanese nuclear power plant of Fukushima Daiichi, the German federal government decided that Germany will give up electricity generation from nuclear power within a decade. The last reactor will be disconnected from the power grid in 2022. Helping to make this opt-out as safe as possible is one of the duties of the Helmholtz Association with its Nuclear Safety Research Program within the Energy Research Area. Also the demolition of nuclear power plants and the repository problem will keep society, and thus also research, busy for a number of decades to come. Giving up electricity production from nuclear power thus must not mean giving up the required nuclear technology competences. In the fields of reactor safety, demolition, final storage, radiation protection, and crisis management, in critical support of international developments, and for competent evaluation of nuclear facilities around Germany, these competences will be in demand far beyond the German opt-out. This is the reason why the final report by the Ethics Committee on 'Safe Energy Supply' emphasizes the importance of nuclear technology research. Close cooperation on national, European and international levels is indispensable in this effort. Also nuclear safety research in the Helmholtz Association is aligned with the challenges posed by the opt-out of the use of nuclear power. It is important that the high competences in the areas of plant safety and demolition, handling of radioactive waste, and safe final storage as well as radiation protection be preserved. The Nuclear Safety Research Program within the Energy Research Area of the Helmholtz Association therefore will continue studying scientific and technical aspects of the safety of nuclear reactors and the safety of nuclear waste management. These research activities are provident research conducted for society and must be preserved for a long period of time. The work is closely harmonized with the activities of the

Advanced I and C systems for nuclear power plants

International Nuclear Information System (INIS)

Bock, H.W.; Graf, A.; Hofmann, H.

1995-01-01

Advanced I and C systems for nuclear power plants have to meet increasing demands for safety and availability. Additionally, specific requirements coming from the nuclear qualification have to be fulfilled. To meet both subjects adequately in the future, Siemens has developed advanced I and C technology consisting of the two complementary I and C systems TELEPERM XP and TELEPERM XS. The main features of these systems are the clear task related architecture with adaptable redundancy, the consequent application of standards for interfaces and communication, comprehensive tools for easy design and service and a highly ergonomic screen based man-machine-interface. The engineering tasks are supported by an integrated engineering system, which has the capacity for design, test and diagnosis of all I and C functions and the related equipment. TELEPERM XP is designed to optimally perform all automatic functions, which require no nuclear specific qualification. This includes all sequences and closed-loop controls as well as most man-machine-interface functions. TELEPERM XS is designed for all control tasks which require a nuclear specific qualification. This especially includes all functions to initiate automatic countermeasures to prevent or to cope with accidents. By use of the complementary I and C systems TELEPERM XP and TELEPERM XS, economical as well as advanced plant automation and man-machine-interfaces can be implemented into Nuclear Plants, assuring the compliance with the relevant international safety standards. (author). 10 figs

Advanced I and C systems for nuclear power plants

International Nuclear Information System (INIS)

Bock, H.W.; Graf, A.; Hofmann, H.

1997-01-01

Advanced I and C systems for nuclear power plants have to meet increasing demands for safety and availability. Additionally specific requirements arising from nuclear qualification have to be fulfilled. To meet both subjects adequately in the future, Siemens has developed advanced I and C technology consisting of the two complementary I and C systems TELEPERM XP and TELEPERM XS. The main features of these systems are a clear task related architecture with adaptable redundancy, a consequent application of standards for interfaces and communication, comprehensive tools for easy design and service and a highly ergonomic screen based man-machine-interface. The engineering tasks are supported by an integrated engineering system, which has the capacity for design, test and diagnosis of all I and C functions and the related equipment. TELEPERM XP is designed to optimally perform all automatic functions, which require no nuclear specific qualification. This includes all sequences and closed-loop controls as well as most man-machine-interface functions. TELEPERM XS is designed for all control tasks which require a nuclear specific qualification. This especially includes all function to initiated automatic countermeasures to prevent or to cope with accidents. By use of the complementary I and C systems TELEPERM XP and TELEPERM XS, advanced and likewise economical plant automation and man-machine-interfaces can be implemented into Nuclear Power Plant, assuring compliance with the relevant international safety standards. (author). 10 figs

Advanced I and C systems for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Bock, H W; Graf, A; Hofmann, H [Siemens AG, Erlangen (Germany)

1997-07-01

Advanced I and C systems for nuclear power plants have to meet increasing demands for safety and availability. Additionally specific requirements arising from nuclear qualification have to be fulfilled. To meet both subjects adequately in the future, Siemens has developed advanced I and C technology consisting of the two complementary I and C systems TELEPERM XP and TELEPERM XS. The main features of these systems are a clear task related architecture with adaptable redundancy, a consequent application of standards for interfaces and communication, comprehensive tools for easy design and service and a highly ergonomic screen based man-machine-interface. The engineering tasks are supported by an integrated engineering system, which has the capacity for design, test and diagnosis of all I and C functions and the related equipment. TELEPERM XP is designed to optimally perform all automatic functions, which require no nuclear specific qualification. This includes all sequences and closed-loop controls as well as most man-machine-interface functions. TELEPERM XS is designed for all control tasks which require a nuclear specific qualification. This especially includes all function to initiated automatic countermeasures to prevent or to cope with accidents. By use of the complementary I and C systems TELEPERM XP and TELEPERM XS, advanced and likewise economical plant automation and man-machine-interfaces can be implemented into Nuclear Power Plant, assuring compliance with the relevant international safety standards. (author). 10 figs.

Nuclear safety research master plan

Energy Technology Data Exchange (ETDEWEB)

Ha, Jae Joo; Yang, J. U.; Jun, Y. S. and others

2001-06-01

The SRMP (Safety Research Master Plan) is established to cope with the changes of nuclear industry environments. The tech. tree is developed according to the accident progress of the nuclear reactor. The 11 research fields are derived to cover the necessary technologies to ensure the safety of nuclear reactors. Based on the developed tech. tree, the following four main research fields are derived as the main safety research areas: 1. Integrated nuclear safety enhancement, 2. Thermal hydraulic experiment and assessment, 3. Severe accident management and experiment, and 4. The integrity of equipment and structure. The research frame and strategies are also recommended to enhance the efficiency of research activity, and to extend the applicability of research output.

Nuclear Medicine

Science.gov (United States)

... Parents/Teachers Resource Links for Students Glossary Nuclear Medicine What is nuclear medicine? What are radioactive tracers? ... funded researchers advancing nuclear medicine? What is nuclear medicine? Nuclear medicine is a medical specialty that uses ...

HSE Nuclear Safety Research Program

Energy Technology Data Exchange (ETDEWEB)

Bagley, M.J. [Health and Safety Executive, Sheffield (United Kingdom)

1995-12-31

HSE funds two programmes of nuclear safety research: a programme of {approx} 2.2M of extramural research to support the Nuclear Safety Division`s regulatory activities and a programme of {approx} 11M of generic safety research managed by the Nuclear Safety Research Management Unit (NSRMU) in Sheffield, UK. This paper is concerned only with the latter programme; it describes how it is planned and procured and outlines some of the work on structural integrity problems. It also describes the changes that are taking place in the way nuclear safety research is procured in the UK. (author).

HSE Nuclear Safety Research Program

International Nuclear Information System (INIS)

Bagley, M.J.

1995-01-01

HSE funds two programmes of nuclear safety research: a programme of ∼ 2.2M of extramural research to support the Nuclear Safety Division's regulatory activities and a programme of ∼ 11M of generic safety research managed by the Nuclear Safety Research Management Unit (NSRMU) in Sheffield, UK. This paper is concerned only with the latter programme; it describes how it is planned and procured and outlines some of the work on structural integrity problems. It also describes the changes that are taking place in the way nuclear safety research is procured in the UK. (author)

Nuclear energy related research

International Nuclear Information System (INIS)

Salminen, P.; Mattila, L.

1990-08-01

The annual Research Programme Plan describes the publicly funded nuclear energy related research to be carried out at the Technical Research Centre of Finland (VTT) in 1990. The research is financed primarily by the Ministry of Trade and Industry (KTM), the Finnish Centre for Radiation and Nuclear Safety (STUK) and VTT itself. Utilities and industry also contribute to some projects

Nuclear Fuel Cycle Analysis Technology to Develop Advanced Nuclear Fuel Cycle

Energy Technology Data Exchange (ETDEWEB)

Park, Byung Heung [Chungju National University, Chungju (Korea, Republic of); Ko, Won IL [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2011-12-15

The nuclear fuel cycle (NFC) analysis is a study to set a NFC policy and to promote systematic researches by analyzing technologies and deriving requirements at each stage of a fuel cycle. System analysis techniques are utilized for comparative analysis and assessment of options on a considered system. In case that NFC is taken into consideration various methods of the system analysis techniques could be applied depending on the range of an interest. This study presented NFC analysis strategies for the development of a domestic advanced NFC and analysis techniques applicable to different phases of the analysis. Strategically, NFC analysis necessitates the linkage with technology analyses, domestic and international interests, and a national energy program. In this respect, a trade-off study is readily applicable since it includes various aspects on NFC as metrics and then analyzes the considered NFC options according to the derived metrics. In this study, the trade-off study was identified as a method for NFC analysis with the derived strategies and it was expected to be used for development of an advanced NFC. A technology readiness level (TRL) method and NFC simulation codes could be utilized to obtain the required metrics and data for assessment in the trade-off study. The methodologies would guide a direction of technology development by comparing and assessing technological, economical, environmental, and other aspects on the alternatives. Consequently, they would contribute for systematic development and deployment of an appropriate advanced NFC.

Nuclear Fuel Cycle Analysis Technology to Develop Advanced Nuclear Fuel Cycle

International Nuclear Information System (INIS)

Park, Byung Heung; Ko, Won IL

2011-01-01

The nuclear fuel cycle (NFC) analysis is a study to set a NFC policy and to promote systematic researches by analyzing technologies and deriving requirements at each stage of a fuel cycle. System analysis techniques are utilized for comparative analysis and assessment of options on a considered system. In case that NFC is taken into consideration various methods of the system analysis techniques could be applied depending on the range of an interest. This study presented NFC analysis strategies for the development of a domestic advanced NFC and analysis techniques applicable to different phases of the analysis. Strategically, NFC analysis necessitates the linkage with technology analyses, domestic and international interests, and a national energy program. In this respect, a trade-off study is readily applicable since it includes various aspects on NFC as metrics and then analyzes the considered NFC options according to the derived metrics. In this study, the trade-off study was identified as a method for NFC analysis with the derived strategies and it was expected to be used for development of an advanced NFC. A technology readiness level (TRL) method and NFC simulation codes could be utilized to obtain the required metrics and data for assessment in the trade-off study. The methodologies would guide a direction of technology development by comparing and assessing technological, economical, environmental, and other aspects on the alternatives. Consequently, they would contribute for systematic development and deployment of an appropriate advanced NFC.

The application of contrast explanation to energy policy research: UK nuclear energy policy 2002–2012

International Nuclear Information System (INIS)

Heffron, Raphael J.

2013-01-01

This paper advances the application of the methodology, contrast explanation, to energy policy research. Research in energy policy is complex and often involves inter-disciplinary work, which traditional economic methodologies fail to capture. Consequently, the more encompassing methodology of contrast explanation is assessed and its use in other social science disciplines explored in brief. It is then applied to an energy policy research topic—in this case, nuclear energy policy research in the UK. Contrast explanation facilitates research into policy and decision-making processes in energy studies and offers an alternative to the traditional economic methods used in energy research. Further, contrast explanation is extended by the addition of contested and uncontested hypotheses analyses. This research focuses on the methods employed to deliver the new nuclear programme of the UK government. In order to achieve a sustainable nuclear energy policy three issues are of major importance: (1) law, policy and development; (2) public administration; and (3) project management. Further, the research identifies that policy in the area remains to be resolved, in particular at an institutional and legal level. However, contrary to the literature, in some areas, the research identifies a change of course as the UK concentrates on delivering a long-term policy for the nuclear energy sector and the overall energy sector. - Highlights: ► Energy policy research is interdisciplinary and needs additional methodological approaches. ► New method of contrast explanation advanced for energy policy research. ► This methodology is based on dialectical learning which examines conflict between sources of data. ► Research example used here is of UK nuclear energy policy. ► Major issues in UK nuclear energy policy are planning law, public administration, and project management

Status of nuclear safety research - 2000

International Nuclear Information System (INIS)

Sobajima, Makoto; Sasajima, Hideo; Umemoto, Michitaka; Yamamoto, Toshihiro; Tanaka, Tadao; Togashi, Yoshihiro; Nakata, Masahito

2000-11-01

The nuclear safety research at JAERI is performed in accordance with the long term plan on nuclear research, development and use and the safety research yearly plan determined by the government and under close relationship to the related departments in and around the Nuclear Safety Research Center. The criticality accident having occurred in Tokai-mura in 1999 has been the highest level nuclear accident in Japan and ensuring safety in whole nuclear cycle is severely questioned. The causes of such an accident have to be clarified not only technical points but also organizational points, and it is extremely important to make efforts in preventing recurrence, to fulfill emergency plan and to improve the safety of whole nuclear fuel cycle for restoring the reliability by the people to nuclear energy system. The fields of conducting safety research are engineering safety research on reactor facilities and nuclear fuel cycle facilities including research on radioactive waste processing and disposal and research and development on future technology for safety improvement. Also, multinational cooperation and bilateral cooperation are promoted in international research organizations in the center to internationally share the recognition of world-common issues of nuclear safety and to attain efficient promotion of research and effective utilization of research resources. (author)

From nuclear research to multidisciplinary research

International Nuclear Information System (INIS)

Theenhaus, R.; Baurmann, K.W.

1996-01-01

Forty years ago, the North Rhine-Westphalian State Government founded the then Juelich Nuclear Research Center. After a growth period of the reactor engineering program until 1980, claiming a share of 42% of R and D resources, that share declined continuously to a present level of 8%. This development is an expression of the activities successfully completed in the past, of progress achieved in industrial reactor development, but also of the fact that the high temperature reactor, which had been run successfully for twenty years, failed as a technical scale THTR-300 version. The Center has reorientated its line of research in a process of structural reshuffle beginning some fifteen years ago and still going on. Information technology, materials research, life sciences, environmental research, and energy technology have become main activities of equal weight. Activities specific to nuclear reactors have been incorporated in this new line of work as nuclear safety research and work on safe repository storage. (orig.) [de

Overview of research potential of Institute for Nuclear Research

International Nuclear Information System (INIS)

Ciocanescu, Marin

2007-01-01

The main organizations involved in nuclear power production in Romania, under supervision of Presidency, Prime Minister and Parliament are: CNCAN (National Commission for Nuclear Activities Control), Nuclear Agency, Ministry of Economy and Commerce, ANDRAD (Waste Management Agency), SNN (Nuclearelectrica National Society), RAAN (Romanian Authority for Nuclear Activities), ICN (Institute for Nuclear Research - Pitesti), SITON (Center of Design and Engineering for Nuclear Projects- Bucharest); ROMAG-PROD (Heavy Water Plant), CNE-PROD (Cernavoda Nuclear Power Plant - Production Unit), CNE-INVEST (Cernavoda Nuclear Power Plant -Investments Unit), FCN (Nuclear Fuel Factory). The Institute for Nuclear Research, Pitesti INR, Institute for Nuclear Research, Pitesti is endowed with a TRIGA Reactor, Hot Cells, Materials Laboratories, Nuclear Fuel, Nuclear Safety Laboratories, Nuclear Fuel, Nuclear Safety. Waste management. Other research centers and laboratories implied in nuclear activities are: ICIT, National Institute for cryogenics and isotope technologies at Rm Valcea Valcea. with R and D activity devoted to heavy water technologies, IFIN, Institute for nuclear physics and engineering, Bucharest, as well as the educational institutions involved in atomic energy applications and University research, Politechnical University Bucharest, University of Bucharest, University of Pitesti, etc. The INR activity outlined, i.e. the nuclear power research as a scientific and technical support for the Romanian nuclear power programme, mainly dedicated to the existing NPP in the country (CANDU). Focused with priority are: - Nuclear Safety (behavior of plant materials, components, installations during accident conditions and integrity investigations); - Radioactive Waste Management Radioactive; - Radioprotection; Product and services supply for NPP. INR Staff numbers 320 R and D qualified and experienced staff, 240 personnel in devices and prototype workshops and site support

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)

Inside CERN European Organization for Nuclear Research

CERN Document Server

Pol, Andri; Heuer, Rolf

2013-01-01

For most people locations that hold a particular importance for the development of our society and for the advancement of science and technology remain hidden from view. CERN, the European Organization for Nuclear Research, is best known for its giant particle accelerator. Here researchers take part in a diverse array of fundamental physical research, in the pursuit of knowledge that will perhaps one dayrevolutionize our understanding of the universe and life on our planet. The Swiss photographer Andri Pol mixed with this multicultural community of researchers and followed their work over an extended period of time. In doing so he created a unique portrait of this fascinating “underworld.” The cutting-edge research is given a human face and the pictures allow us to perceive how in this world of the tiniest particles the biggest connections are searched for. With an essay by Peter Stamm.

Tehran Nuclear Research Center

International Nuclear Information System (INIS)

Taherzadeh, M.

1977-01-01

The Tehran Nuclear Research Center was formerly managed by the University of Tehran. This Center, after its transformation to the AEOI, has now become a focal point for basic research in the area of Nuclear Energy in Iran

Nuclear energy research in Indonesia

International Nuclear Information System (INIS)

Supadi, S.; Soentono, S.; Djokolelono, M.

1988-01-01

Indonesia's National Atomic Energy Authority, BATAN (Badan Tenaga Atom Nasional), was founded to implement, regulate and monitor the development and launching of programs for the peaceful uses of nuclear power. These programs constitute part of the efforts made to change to a more industrialized level the largely agricultural society of Indonesia. BATAN elaborated extensive nuclear research and development programs in a variety of fields, such as medicine, the industrial uses of isotopes and radiation, the nuclear fuel cycle, nuclear technology and power generation, and in fundamental research. The Puspiptek Nuclear Research Center has been equipped with a multi-purpose research reactor and will also have a fuel element fabrication plant, a facility for treating radioactive waste, a radiometallurgical laboratory, and laboratories for working with radioisotopes and for radiopharmaceutical research. (orig.) [de

Utilization of nuclear research reactors

International Nuclear Information System (INIS)

1980-01-01

prior to the beginning of the course was of particular value. Interesting scientific visits and demonstrations at the Isotope Institute and at the Central Research Institute for Physics (IFKI), both of the Hungarian Academy of Sciences, were also arranged. During the Study Tour at the Central Institute for Nuclear Research in Rossendorf near Dresden, German Democratic Republic, the participants had the opportunity to observe the organization of a 10 MW nuclear reactor where radioisotopes and radiopharmaceuticals are produced on a commercial scale. Lectures were delivered by local scientists on some of their programmes in applied research in solid state physics and material sciences. At the Technical University of Dresden, the group visited the homogeneous solid-moderated zero-power training reactor (AKR), primarily dedicated to nuclear education and training. Studies on different theoretical and experimental aspects of radiation protection (solid state nuclear track and thermoluminescent detectors) are also being carried out. The last day of the Study Tour was devoted to a visit to the College for Advanced Technology at Zittau, where a training reactor with a power of a few watts has been recently installed. (author)

Progress of nuclear safety research, 1990

International Nuclear Information System (INIS)

1990-07-01

Since the Japan Atomic Energy Research Institute (JAERI) was founded as a nonprofit, general research and development organization for the peaceful use of nuclear energy, it has actively pursued the research and development of nuclear energy. Nuclear energy is the primary source of energy in Japan where energy resources are scarce. The safety research is recognized at JAERI as one of the important issues to be clarified, and the safety research on nuclear power generation, nuclear fuel cycle, waste management and environmental safety has been conducted systematically since 1973. As of the end of 1989, 38 reactors were in operation in Japan, and the nuclear electric power generated in 1988 reached 29 % of the total electric power generated. 50 years have passed since nuclear fission was discovered in 1939. The objective of the safety research at JAERI is to earn public support and trust for the use of nuclear energy. The overview of the safety research at JAERI, fuel behavior, reliability of reactor structures and components, reactor thermal-hydraulics during LOCA, safety assessment of nuclear power plants and nuclear fuel cycle facilities, radioactive waste management and environmental radioactivity are reported. (K.I.)

Future for nuclear data research. Human resources

International Nuclear Information System (INIS)

Baba, Mamoru

2006-01-01

A comment is given on the problem of human resources to support the future nuclear data activity which will be indispensable for advanced utilization of nuclear energy and radiations. Emphasis is put in the importance of the functional organization among the nuclear data center (JAEA), industries and universities for provision of human resources. (author)

Basic research and industrialization of CANDU advanced fuel

Energy Technology Data Exchange (ETDEWEB)

Chun, Suk Ho; Park, Joo Hwan; Jun, Ji Su [and others

2000-04-01

Wolsong Unit 1 as the first heavy water reactor in Korea has been in service for 17 years since 1983. It would be about the time to prepare a plan for the solution of problems due to aging of the reactor. The aging of CANDU reactor could lead especially to the steam generator cruding and pressure tube sagging and creep and then decreases the operation margin to make some problems on reactor operations and safety. The counterplan could be made in two ways. One is to repair or modify reactor itself. The other is to develop new advanced fuel to increase of CANDU operation margin effectively, so as to compensate the reduced operation margin. Therefore, the first objectives in the present R and D is to develop the CANFLEX-NU (CANDU Flexible fuelling-Natural Uranium) fuel as a CANDU advanced fuel. The second objectives is to develop CANDU advanced fuel bundle to utilize advanced fuel cycles such as recovered uranium, slightly enriched uranium, etc. and so to raise adaptability for change in situation of uranium market. Also, it is to develop CANDU advanced fuel technology which improve uranium utilization to cope with a world-wide imbalance between uranium supply and demand, without significant modification of nuclear reactor design and refuelling strategies. As the implementations to achieve the above R and D goal, the work contents and scope of technology development of CANDU advanced fuel using natural uranium (CANFLEX-NU) are the fuel element/bundle designs, the nuclear design and fuel management analysis, the thermalhydraulic analysis, the safety analysis, fuel fabrication technologies, the out-pile thermalhydraulic test and in-pile irradiation tests performed. At the next, the work scopes and contents of feasibility study of CANDU advanced fuel using recycled uranium (CANFLEX-RU) are the fuel element/bundle designs, the reactor physics analysis, the thermalhydraulic analysis, the basic safety analysis of a CANDU-6 reactor with CANFLEX-RU fuel, the fabrication and

Basic research and industrialization of CANDU advanced fuel

International Nuclear Information System (INIS)

Chun, Suk Ho; Park, Joo Hwan; Jun, Ji Su

2000-04-01

Wolsong Unit 1 as the first heavy water reactor in Korea has been in service for 17 years since 1983. It would be about the time to prepare a plan for the solution of problems due to aging of the reactor. The aging of CANDU reactor could lead especially to the steam generator cruding and pressure tube sagging and creep and then decreases the operation margin to make some problems on reactor operations and safety. The counterplan could be made in two ways. One is to repair or modify reactor itself. The other is to develop new advanced fuel to increase of CANDU operation margin effectively, so as to compensate the reduced operation margin. Therefore, the first objectives in the present R and D is to develop the CANFLEX-NU (CANDU Flexible fuelling-Natural Uranium) fuel as a CANDU advanced fuel. The second objectives is to develop CANDU advanced fuel bundle to utilize advanced fuel cycles such as recovered uranium, slightly enriched uranium, etc. and so to raise adaptability for change in situation of uranium market. Also, it is to develop CANDU advanced fuel technology which improve uranium utilization to cope with a world-wide imbalance between uranium supply and demand, without significant modification of nuclear reactor design and refuelling strategies. As the implementations to achieve the above R and D goal, the work contents and scope of technology development of CANDU advanced fuel using natural uranium (CANFLEX-NU) are the fuel element/bundle designs, the nuclear design and fuel management analysis, the thermalhydraulic analysis, the safety analysis, fuel fabrication technologies, the out-pile thermalhydraulic test and in-pile irradiation tests performed. At the next, the work scopes and contents of feasibility study of CANDU advanced fuel using recycled uranium (CANFLEX-RU) are the fuel element/bundle designs, the reactor physics analysis, the thermalhydraulic analysis, the basic safety analysis of a CANDU-6 reactor with CANFLEX-RU fuel, the fabrication and

Japanese Strategy for Nuclear Energy Research and Development For the Future

Energy Technology Data Exchange (ETDEWEB)

Ihara, Yoshinori [Japan Atomic Energy Research Institute, Tokyo (Japan)

1988-04-15

As for the research and development of nuclear energy, the future is, I believe, very broad, deep and promising and there are still unnoticed frontiers whose development will give rise to the evolution of human society. In order to cultivate the frontiers we should have insight to distinguish what is fundamental and essential from what in not. We should also have a fighting spirit to challenge our dream. The Japan Atomic Energy Research Institute really wishes to become the place where many scientists and engineers from abroad meet and work with US with insight and a pioneering spirit. About thirty years ago, the first version of the Japanese 'Long-Term Program for Development and Utilization of Nuclear Energy' was drawn up by the Atomic Energy Commission for the first time. Since then, the Long-Term Program has been revised once every five years. The research, development and utilization of nuclear energy in Japan have been guided by the Long-Term Program, and it has clearly shown the Japanese strategy for Nuclear Energy R and D for the future at each stage of the for Nuclear Energy R and D for the future at each stage of the history. The latest version of the Long-Term Program was published in June 1987. It defines the outline of the philosophy and the scheme for promoting the basic measures related to the research, development and utilization of nuclear energy up to the year 2000 based on the long-range nuclear energy policy towards the 21st century. This Long-Term Program was drawn up by taking into consideration the essential changes of the by taking into consideration the essential changes of the environment surrounding nuclear energy during recent years from the viewpoints of the supply and demand for energy, the rise of public concern for nuclear safety, the role of nuclear research and development for the advancement of science and technology, and the international nuclear energy issues. In this article, the author would like to describe the basic

Japanese Strategy for Nuclear Energy Research and Development For the Future

International Nuclear Information System (INIS)

Ihara, Yoshinori

1988-01-01

As for the research and development of nuclear energy, the future is, I believe, very broad, deep and promising and there are still unnoticed frontiers whose development will give rise to the evolution of human society. In order to cultivate the frontiers we should have insight to distinguish what is fundamental and essential from what in not. We should also have a fighting spirit to challenge our dream. The Japan Atomic Energy Research Institute really wishes to become the place where many scientists and engineers from abroad meet and work with US with insight and a pioneering spirit. About thirty years ago, the first version of the Japanese 'Long-Term Program for Development and Utilization of Nuclear Energy' was drawn up by the Atomic Energy Commission for the first time. Since then, the Long-Term Program has been revised once every five years. The research, development and utilization of nuclear energy in Japan have been guided by the Long-Term Program, and it has clearly shown the Japanese strategy for Nuclear Energy R and D for the future at each stage of the for Nuclear Energy R and D for the future at each stage of the history. The latest version of the Long-Term Program was published in June 1987. It defines the outline of the philosophy and the scheme for promoting the basic measures related to the research, development and utilization of nuclear energy up to the year 2000 based on the long-range nuclear energy policy towards the 21st century. This Long-Term Program was drawn up by taking into consideration the essential changes of the by taking into consideration the essential changes of the environment surrounding nuclear energy during recent years from the viewpoints of the supply and demand for energy, the rise of public concern for nuclear safety, the role of nuclear research and development for the advancement of science and technology, and the international nuclear energy issues. In this article, the author would like to describe the basic

Importance of Advanced Planning of Manufacturing for Nuclear Industry

Directory of Open Access Journals (Sweden)

Shykinov Nick

2016-06-01

Full Text Available In the context of energy demands by growing economies, climate changes, fossil fuel pricing volatility, and improved safety and performance of nuclear power plants, many countries express interest in expanding or acquiring nuclear power capacity. In the light of the increased interest in expanding nuclear power the supply chain for nuclear power projects has received more attention in recent years. The importance of the advanced planning of procurement and manufacturing of components of nuclear facilities is critical for these projects. Many of these components are often referred to as long-lead items. They may be equipment, products and systems that are identified to have a delivery time long enough to affect directly the overall timing of a project. In order to avoid negatively affecting the project schedule, these items may need to be sourced out or manufactured years before the beginning of the project. For nuclear facilities, long-lead items include physical components such as large pressure vessels, instrumentation and controls. They may also mean programs and management systems important to the safety of the facility. Authorized nuclear operator training, site evaluation programs, and procurement are some of the examples. The nuclear power industry must often meet very demanding construction and commissioning timelines, and proper advanced planning of the long-lead items helps manage risks to project completion time. For nuclear components there are regulatory and licensing considerations that need to be considered. A national nuclear regulator must be involved early to ensure the components will meet the national legal regulatory requirements. This paper will discuss timing considerations to address the regulatory compliance of nuclear long-lead items.

Nuclear energy research until 2000

International Nuclear Information System (INIS)

Reiman, L.; Rintamaa, R.; Vanttola, T.

1994-03-01

The working group was to assess the need and orientation of nuclear energy research (apart from research on nuclear waste management and fusion technology) up until the year 2000 in Finland and to propose framework schemes and organization guidelines for any forthcoming publicly financed research programmes from 1995 onwards. The main purpose of nuclear energy research is to ensure the safety and continued development of Finland's existing nuclear power plants. Factors necessarily influencing the orientation of research are Parliaments decision of late 1993 against further nuclear capacity in the country, the need to assess reactor safety in the eastern neighbour regions, and Finland's potential membership in the European Union. The working group proposes two new research programmes similar to the current ones but with slightly modified emphasis. Dedicated to reactor safety and structural safety respectively, they would both cover the four years from 1995 to 1998. A separate research project is proposed for automation technology. In addition, environmental research projects should have a joint coordination unit. (9 figs., 4 tabs.)

Materials technologies for advanced nuclear energy concepts

International Nuclear Information System (INIS)

DiStefano, J.; Harms, B.

1983-01-01

High-performance, advanced nuclear power plant concepts have emerged with major emphasis on lower capital costs, inherent safety, and increased reliability. The materials problems posed by these concepts are discussed and how the scientists and technologists at ORNL plan to solve them is described

Design study of advanced nuclear fuel recycle system. Conceptual study of recycle system using molten salt

International Nuclear Information System (INIS)

Kakehi, I.; Shirai, N.; Hatano, M.; Kajitani, M.; Yonezawa, S.; Kawai, T.; Kawamura, F.; Tobe, K.; Takahashi, K.

1996-12-01

For the purpose of developing the future nuclear fuel recycle system, the design study of the advanced nuclear fuel recycle system is being conducted. This report describes intermediate accomplishments in the conceptual system study of the advanced nuclear fuel recycle system. Fundamental concepts of this system is the recycle system using molten salt which intend to break through the conventional concepts of purex and pellet fuel system. Contents of studies in this period are as follows, 1)feasibility study of the process by Cd-cathode for nitride fuel, 2)application study for the molten salt of low melting point (AlCl3+organic salt), 3)research for decladding (advantage of decladding by heat treatment), 4)behavior of FPs in electrorefining (behavior of iodine and volatile FP chlorides, FPs behavior in chlorination), 5)criticality analysis in electrorefiner, 6)drawing of off-gas flow diagram, 7)drawing of process machinery concept (cathode processor, vibration packing), 8)evaluation for the amounts of the high level radioactive wastes, 9)quality of the recycle fuels (FPs contamination of recycle fuel), 10)conceptual study of in-cell handling system, 11)meaning of the advanced nuclear fuel recycle system. The conceptual system study will be completed in describing concepts of the system and discussing issues for the developments. (author)

Providing Policy Implication Based on the R and D Portfolio Analysis in Advanced Countries in the Nuclear Technology

Energy Technology Data Exchange (ETDEWEB)

Moon, K. H.; Lee, M. K.; Won, B. C.; Kim, S. S.; Lee, J. H.; Yun, S. W.; Jeong, I. K.; Lee, Y. C.; Lee, Y. J.; Kim, Y. S.

2013-08-15

This study is to provide the investment direction of nuclear R and D, which is the most efficient and reasonable integrating the various aspects comprehensively. This study includes four parts. In the first part, we extracted Mega-trend and driving forces of nuclear R and D field by using various reports published by National Intelligence Council of US, UN, etc. Also, in this part we established the linkage between megatrend factors focussing on nuclear and the five aspects including society, technology, ecology, economics and politics. In the second part, we analyzed the nuclear R and D investment directions of major advanced countries including US, Japan, EU and China for comparing the investment portfolio in the specific research area. In the third part, domestic investment of nuclear R and D was reviewed by analyzing the investment trend of nuclear R and D in the past, with their connection to nuclear policy, and to the levels and capacities of national technologies of nuclear. In the final part, the desirable directions of nuclear R and D investment were suggested comprehensively taking into consideration various aspects including the Mega-trend associated with nuclear, nuclear R and D directions of major advanced countries, and the level and capacities of the domestic nuclear technologies.

Providing Policy Implication Based on the R and D Portfolio Analysis in Advanced Countries in the Nuclear Technology

International Nuclear Information System (INIS)

Moon, K. H.; Lee, M. K.; Won, B. C.; Kim, S. S.; Lee, J. H.; Yun, S. W.; Jeong, I. K.; Lee, Y. C.; Lee, Y. J.; Kim, Y. S.

2013-08-01

This study is to provide the investment direction of nuclear R and D, which is the most efficient and reasonable integrating the various aspects comprehensively. This study includes four parts. In the first part, we extracted Mega-trend and driving forces of nuclear R and D field by using various reports published by National Intelligence Council of US, UN, etc. Also, in this part we established the linkage between megatrend factors focussing on nuclear and the five aspects including society, technology, ecology, economics and politics. In the second part, we analyzed the nuclear R and D investment directions of major advanced countries including US, Japan, EU and China for comparing the investment portfolio in the specific research area. In the third part, domestic investment of nuclear R and D was reviewed by analyzing the investment trend of nuclear R and D in the past, with their connection to nuclear policy, and to the levels and capacities of national technologies of nuclear. In the final part, the desirable directions of nuclear R and D investment were suggested comprehensively taking into consideration various aspects including the Mega-trend associated with nuclear, nuclear R and D directions of major advanced countries, and the level and capacities of the domestic nuclear technologies

Nuclear energy research in Germany 2009

International Nuclear Information System (INIS)

2010-01-01

Research and development (R and D) in the fields of nuclear reactor safety and safety of nuclear waste and spent fuel management in Germany are carried out at research centers and, in addition, some 32 universities. In addition, industrial research is conducted by plant vendors, and research in plant and operational safety of power plants in operation is organized by operators and by organizations of technical and scientific research and expert consultant organizations. This summary report presents nuclear energy research conducted at research centers and universities in Germany in 2009, including examples of research projects and descriptions of the situation of research and teaching. These are the organizations covered: - Hermann von Helmholtz Association of German Research Centers, - Karlsruhe Institute of Technology (KIT, responsibility of the former Karlsruhe Research Center), - Juelich Research Center (FZJ), - Nuclear Technology Competence Center East, - Dresden-Rossendorf Research Center (FZD), - Rossendorf Nuclear Process Technology and Analysis Association (VKTA), - Dresden Technical University, - Zittau/Goerlitz University of Applied Science, - Institute of Nuclear Energy and Energy Systems (IKE) of the University of Stuttgart. (orig.)

Nuclear plant aging research - an overview (electrical and mechanical components)

International Nuclear Information System (INIS)

Vora, J.P.

1985-01-01

As the operating nuclear power plants advance in age there must be a conscious national and international effort to understand the influence and safety implications of aging and service wear of components and structures in nuclear power plants and develop measures which are practical and cost effective for timely mitigation of aging degradation that could significantly affect plant safety. The Office of Nuclear Regulatory Research has, therefore, initiated a multi-year, multi-disciplinary program on Nuclear Plant Aging Research (NPAR). The overall goals identified for the program are as follows: 1) to identify and characterize aging and service wear effects associated with electrical and mechanical components, interfaces, and systems whose failure could impair plant safety; 2) to identify and recommend methods of inspection, surveillance and condition monitoring of electrical and mechanical components and systems which will be effective in detecting significant aging effects prior to loss of safety function so that timely maintenance and repair or replacement can be implemented; and, 3) to identify and recommend acceptable maintenance practices which can be undertaken to mitigate the effects of aging and to diminish the rate and extent of degradation caused by aging and service wear. The specific research activities to be implemented to achieve these goals are described

Nuclear techniques in the coal industry. Proceedings of a final research co-ordination meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-11-01

With the aim of promoting advanced research and facilitating a more extensive application of nuclear techniques for environmental protection in the exploration and exploitation of coal, the IAEA established the present co-ordinated research programme (CRP) in 1989. This report includes an assessment of the current status and trends in nuclear techniques in the coal industry and the results obtained by the participants at the CRP. Proceedings of the final CRP on ``Nuclear Techniques in Exploration and Exploitation of Coal: On-line and Bulk Analysis and Evaluation of Potential Environmental Pollutants in Coal and Coke``, was held in Krakow, Poland, from 9 to 12 May 1994. Refs, figs, tabs.

Nuclear desalination in the Arab world - Part II: Advanced inherent and passive safe nuclear reactors

International Nuclear Information System (INIS)

Karameldin, A.; Samer S. Mekhemar

2004-01-01

Rapid increases in population levels have led to greater demands for fresh water and electricity in the Arab World. Different types of energies are needed to contribute to bridging the gap between increased demand and production. Increased levels of safeguards in nuclear power plants have became reliable due to their large operational experience, which now exceeds 11,000 years of operation. Thus, the nuclear power industry should be attracting greater attention. World electricity production from nuclear power has risen from 1.7% in 1970 to 17%-20% today. This ratio had increased in June 2002 to reach more than 30%, 33% and 42% in Europe, Japan, and South Korea respectively. In the Arab World, both the public acceptance and economic viability of nuclear power as a major source of energy are greatly dependent on the achievement of a high level of safety and environmental protection. An assessment of the recent generation of advanced reactor safety criteria requirements has been carried out. The promising reactor designs adapted for the Arab world and other similar developing countries are those that profit from the enhanced and passive safety features of the new generation of reactors, with a stronger focus on the effective use of intrinsic characteristics, simplified plant design, and easy construction, operation and maintenance. In addition, selected advanced reactors with a full spectrum from small to large capacities, and from evolutionary to radical types, which have inherent and passive safety features, are discussed. The relevant economic assessment of these reactors adapted for water/electricity cogeneration have been carried out and compared with non-nuclear desalination methods. This assessment indicates that, water/electricity cogeneration by the nuclear method with advanced inherent and passive safe nuclear power plants, is viable and competitive. (author)

Plasma Physics and Controlled Nuclear Fusion Research 1971. Vol. III. Proceedings of the Fourth International Conference on Plasma Physics and Controlled Nuclear Fusion Research

International Nuclear Information System (INIS)

1971-01-01

The ultimate goal of controlled nuclear fusion research is to make a new energy source available to mankind, a source that will be virtually unlimited and that gives promise of being environmentally cleaner than the sources currently exploited. This goal has stimulated research in plasma physics over the past two decades, leading to significant advances in the understanding of matter in its most common state as well as to progress in the confinement and heating of plasma. An indication of this progress is that in several countries considerable effort is being devoted to design studies of fusion reactors and to the technological problems that will be encountered in realizing these reactors. This range of research, from plasma physics to fusion reactor engineering, is shown in the present three-volume publication of the Proceedings of the Fourth Conference on Plasma Physics and Controlled Nuclear Fusion Research. The Conference was sponsored by the International Atomic Energy Agency and was held in Madison, Wisconsin, USA from 17 to 23 June 1971. The enthusiastic co-operation of the University of Wisconsin and of the United States Atomic Energy Commission in the organization of the Conference is gratefully acknowledged. The Conference was attended by over 500 scientists from 24 countries and 3 international organizations, and 143 papers were presented. These papers are published here in the original language; English translations of the Russian papers will be published in a Special Supplement to the journal Nuclear Fusion. The series of conferences on Plasma Physics and Controlled Nuclear Fusion Research has become a major international forum for the presentation and discussion of results in this important and challenging field. In addition to sponsoring these conferences, the International Atomic Energy Agency supports controlled nuclear fusion research by publishing the journal Nuclear Fusion, and has recently established an International Fusion Research Council

Advance of investigation of irradiation embrittlement mechanism of nuclear reactor pressure vessel steels. History and future of irradiation embrittlement researches

International Nuclear Information System (INIS)

Ishino, Shiori

2007-01-01

The nuclear reactor pressure vessel is the most important component of LWR plants required to be safe. This paper describes contents of the title consisting of four chapters. The first chapter states the general theory of irradiation effects, irradiation embrittlement and decreasing of toughness, and some kinds of pressure vessel steels. The second chapter explains history of irradiation embrittlement investigations and the advance of research methods for experiments and calculation. The third chapter contains information of inner structure of irradiated materials and development of prediction equations, recent information of embrittlement mechanism and mechanism guided prediction method, USA model and Central Research Institute of Electric Power Industry (CRIEPI) model. The fourth chapter states recent problems from viewpoints of experimental and analytical approaches. Comparison of standards of LWR pressure vessel steels between Japan and USA, relation between the density of number of cluster and the copper content, effect of flux on clustering of copper atoms, and CRIEPI's way of approaching the prediction method are illustrated. (S.Y.)

Plan for research to improve the safety of light-water nuclear power plants

International Nuclear Information System (INIS)

1978-03-01

This is the U.S. Nuclear Regulatory Commission's first annual report to Congress on recommendations for research on improving the safety of light-water nuclear power plants. Suggestions for reactor safety research were identified in, or received from, various sources, including the Advisory Committee on Reactor Safeguards, the NRC regulatory staff, and the consultants to the Research Review Group. After an initial screening to eliminate those not related to improved reactor safety, all the suggestions were consolidated into research topics. It is recommended that the following research projects be carried out: alternate containment concepts, especially vented containments; alternate decay heat removal concepts, especially add-on bunkered systems; alternate emergency core cooling concepts; improved in-plant accident response; and advanced seismic designs

Nuclear physics research report 1988

International Nuclear Information System (INIS)

1988-01-01

The paper presents the 1988 Nuclear Physics Research Report for the University of Surrey, United Kingdom. The report includes both experimental nuclear structure physics and theoretical nuclear physics research work. The experimental work has been carried out predominantly with the Nuclear Structure Facility at the SERC Daresbury Laboratory, and has concerned nuclear shapes, shape coexistence, shape oscillations, single-particle structures and neutron-proton interaction. The theoretical work has involved nuclear reactions with a variety of projectiles below 1 GeV per nucleon incident energy, and aspects of hadronic interactions at intermediate energies. (U.K.)

Advanced directions of peaceful applications of nuclear energy in the Republic of Azerbaijan

International Nuclear Information System (INIS)

Garibov, A.A.

2006-01-01

Full text: Application of nuclear energy is actual during last years due to depletion of organic sources of row materials. Therefore, each country develops the programs on peaceful application of nuclear energy and using alternative as well as other energy sources on the basis of the analysis of fuel-energy balance and energy demand state. The Republic of Azerbaijan has huge hydrocarbon resources and alternative energy sources. However, taking into account the fact that hydrocarbon resources can cover increasing energy demand at maximum 50-60 years and renewable energy sources can not meet large energy demand during near future then the discovering of advanced ways on peaceful application of nuclear energy is of great importance. Since the seventies of the twentieth century, wide spectrum of scientific researches on the discovering advanced ways on peaceful application of nuclear energy are carried out in the Republic of Azerbaijan. Among them it is necessary to mark the following directions: radiation modification of the properties of polymers, absorbents, catalysts, metals and alloys, semiconductors, dielectrics, ferroelectrics and various devices; radiation oil-chemistry processes; radiation polymerization; radiation-heterogeneous processes; atomic-hydrogen energy; scientific problems of radiation safety and nuclear security; discovering possibilities for using radiation technologies in the solution of environmental problems; radiation sciences of materials and radiation physics; radiation biology and medicine; application of isotope sources in medicine; application of isotope in oil-gas industry; application of isotope sources in radiography and different fields of technique

Report of the summative evaluation by the advisory committee on nuclear safety research

International Nuclear Information System (INIS)

2005-03-01

The Research Evaluation Committee of the Japan Atomic Energy Research Institute (JAERI) set up an Advisory Committee on Nuclear Safety Research in accordance with the 'Fundamental Guideline for the Evaluation of Research and Development (R and D) at JAERI' and its subsidiary regulations. The Advisory Committee on Nuclear Safety Research evaluated the adequacy of the plans of nuclear safety research to be succeeded from JAERI to a new research institute which will be established by integration of JAERI and the Japan Nuclear Cycle Development Institute (JNC). The Advisory Committee consisted of eight specialists from outside the JAERI conducted its activities from June 2004 to August 2004. The evaluation was performed on the basis of the materials submitted in advanced and of the oral presentations made at the Advisory Committee meeting which was held on July 27, 2004, in line with the items, viewpoints, and criteria for the evaluation specified by the Research Evaluation Committee. The result of the evaluation by the Advisory Committee was submitted to the Research Evaluation Committee, and was judged to be appropriate at its meeting held on December 1, 2004. This report describes the result of the evaluation by the Advisory Committee on Safety Research. (author)

Research on applicability of optical and digital technologies to nuclear power stations

International Nuclear Information System (INIS)

Emoto, Motonori

1990-01-01

Recently, the development of electronic technology represented by optical multiple transmission technology and digital technology is remarkable, and it is expected that this tendency advances further hereafter. The improvement of the reliability, operational performance and maintainability of nuclear power stations by applying these most advanced technologies to them has been desired. In this research, it was found that by the application of optical multiple transmission and digital technology to nuclear power stations, their operation by a small number of operators, the automation of work management and so on can be realized. Besides, it was found that as the major technologies of hereafter, the advance of artificial intelligence technology, rapid and large capacity information processing, the network of the computers of different types and others is necessary. Further, if these technologies are completed, the clarification of the requirement when those are actually applied to nuclear power stations is necessary, and it was found also that as the matters to be considered at that time, the extent of improvement of reliability, the reduction of risk at the time of the troubles of equipment and other fundamental matters must be clarified hereafter. (K.I.)

Advancing against nuclear terrorism

International Nuclear Information System (INIS)

Allison, G.

2006-01-01

Meeting a day before the summit, Bush and Putin announced a new Global Initiative to Combat Nuclear Terrorism; a plan for multiple, multilateral guaranteed suppliers of nuclear fuel to States that forgo building their own enrichment plants; and a Civil Nuclear Agreement that will lift restrictions on cooperation between the two countries in developing peaceful nuclear power. Each of these initiatives provides a framework for dozens of specific actions that can measurably reduce the risk of terrorists acquiring a nuclear weapon. The significance of the Global Initiative against Nuclear Terrorism lies not only in its substance but in Russia's visible joint ownership of the Initiative. After years in which Washington lectured Moscow about this threat, Putin's joint leadership in securing nuclear material worldwide should give added impetus to this undertaking inside Russia as well. Globally, this initiative calls for work plans in five arenas: prevention, detection, disruption, mitigation of consequences after an attack, and strengthening domestic laws and export controls against future A.Q. Khans. The guaranteed nuclear fuel supply tightens the noose around Iran as it seeks to exploit a loophole in the global Nuclear Non-Proliferation Treaty. By guaranteeing States that six separate international suppliers will provide backup guarantees against interruption of supply for any reason other that breech of commitments under the NPT, this proposal eliminates Iran's excuse for Natanz-the enrichment plant it is rushing to finish today. This system for supply will be subject to the supervision by the IAEA, which will also have nuclear fuel reserves that allow it to be a supplier of last resort. The Civil Nuclear Agreement will allow joint research on next-generation, proliferation-proof reactors, including technologies where Russian science is the best in the world. It will permit sale to Russia of US technologies that can improve the safety and efficiency of Russian nuclear

Review of research on advanced computational science in FY2016

International Nuclear Information System (INIS)

2017-12-01

Research on advanced computational science for nuclear applications, based on “Plan to Achieve Medium- to Long-term Objectives of the Japan Atomic Energy Agency (Medium- to Long-term Plan)”, has been performed at Center for Computational Science and e-Systems (CCSE), Japan Atomic Energy Agency. CCSE established the committee consisting of outside experts and authorities which does research evaluation and advices for the assistance of the research and development. This report summarizes the followings. (1) Results of the R and D performed at CCSE in FY 2016 (April 1st, 2016 - March 31st, 2017), (2) Results of the evaluation on the R and D by the committee in FY 2016. (author)

Nuclear Energy Research Initiative. Risk Informed Assessment of Regulatory and Design Requirements for Future Nuclear Power Plants. Annual Report

International Nuclear Information System (INIS)

Ritterbusch, S.E.

2000-01-01

The overall goal of this research project is to support innovation in new nuclear power plant designs. This project is examining the implications, for future reactors and future safety regulation, of utilizing a new risk-informed regulatory system as a replacement for the current system. This innovation will be made possible through development of a scientific, highly risk-informed approach for the design and regulation of nuclear power plants. This approach will include the development and.lor confirmation of corresponding regulatory requirements and industry standards. The major impediment to long term competitiveness of new nuclear plants in the U.S. is the capital cost component--which may need to be reduced on the order of 35% to 40% for Advanced Light Water Reactors (ALWRs) such as System 80+ and Advanced Boiling Water Reactor (ABWR). The required cost reduction for an ALWR such as AP600 or AP1000 would be expected to be less. Such reductions in capital cost will require a fundamental reevaluation of the industry standards and regulatory bases under which nuclear plants are designed and licensed. Fortunately, there is now an increasing awareness that many of the existing regulatory requirements and industry standards are not significantly contributing to safety and reliability and, therefore, are unnecessarily adding to nuclear plant costs. Not only does this degrade the economic competitiveness of nuclear energy, it results in unnecessary costs to the American electricity consumer. While addressing these concerns, this research project will be coordinated with current efforts of industry and NRC to develop risk-informed, performance-based regulations that affect the operation of the existing nuclear plants; however, this project will go farther by focusing on the design of new plants

Nuclear Energy Research Initiative. Risk Informed Assessment of Regulatory and Design Requirements for Future Nuclear Power Plants. Annual Report

Energy Technology Data Exchange (ETDEWEB)

Ritterbusch, S.E.

2000-08-01

The overall goal of this research project is to support innovation in new nuclear power plant designs. This project is examining the implications, for future reactors and future safety regulation, of utilizing a new risk-informed regulatory system as a replacement for the current system. This innovation will be made possible through development of a scientific, highly risk-informed approach for the design and regulation of nuclear power plants. This approach will include the development and.lor confirmation of corresponding regulatory requirements and industry standards. The major impediment to long term competitiveness of new nuclear plants in the U.S. is the capital cost component--which may need to be reduced on the order of 35% to 40% for Advanced Light Water Reactors (ALWRs) such as System 80+ and Advanced Boiling Water Reactor (ABWR). The required cost reduction for an ALWR such as AP600 or AP1000 would be expected to be less. Such reductions in capital cost will require a fundamental reevaluation of the industry standards and regulatory bases under which nuclear plants are designed and licensed. Fortunately, there is now an increasing awareness that many of the existing regulatory requirements and industry standards are not significantly contributing to safety and reliability and, therefore, are unnecessarily adding to nuclear plant costs. Not only does this degrade the economic competitiveness of nuclear energy, it results in unnecessary costs to the American electricity consumer. While addressing these concerns, this research project will be coordinated with current efforts of industry and NRC to develop risk-informed, performance-based regulations that affect the operation of the existing nuclear plants; however, this project will go farther by focusing on the design of new plants.

U.S. Department of Energy instrumentation and controls technology research for advanced small modular reactors

International Nuclear Information System (INIS)

Wood, Richard Thomas

2013-01-01

Instrumentation, controls, and human-machine interfaces (ICHMI) are essential enabling technologies that strongly influence nuclear power plant performance and operational costs. The U.S. Department of Energy (DOE) has recognized that ICHMI research, development, and demonstration (RD and D) is needed to resolve the technical challenges that may compromise the effective and efficient utilization of modern ICHMI technology and consequently inhibit realization of the benefits offered by expanded utilization of nuclear power. Consequently, key DOE programs have substantial ICHMI RD and D elements to their respective research portfolio. This article describes current ICHMI research to support the development of advanced small modular reactors. (author)

Historical perspectives - The role of the NASA Lewis Research Center in the national space nuclear power programs

Science.gov (United States)

Bloomfield, H. S.; Sovie, R. J.

1991-01-01

The history of the NASA Lewis Research Center's role in space nuclear power programs is reviewed. Lewis has provided leadership in research, development, and the advancement of space power and propulsion systems. Lewis' pioneering efforts in nuclear reactor technology, shielding, high temperature materials, fluid dynamics, heat transfer, mechanical and direct energy conversion, high-energy propellants, electric propulsion and high performance rocket fuels and nozzles have led to significant technical and management roles in many natural space nuclear power and propulsion programs.

Historical perspectives: The role of the NASA Lewis Research Center in the national space nuclear power programs

Science.gov (United States)

Bloomfield, H. S.; Sovie, R. J.

1991-01-01

The history of the NASA Lewis Research Center's role in space nuclear power programs is reviewed. Lewis has provided leadership in research, development, and the advancement of space power and propulsion systems. Lewis' pioneering efforts in nuclear reactor technology, shielding, high temperature materials, fluid dynamics, heat transfer, mechanical and direct energy conversion, high-energy propellants, electric propulsion and high performance rocket fuels and nozzles have led to significant technical and management roles in many national space nuclear power and propulsion programs.

Nuclear safety research in HGF 2012

International Nuclear Information System (INIS)

Anon.

2013-01-01

After the events at the Japanese nuclear power plant of Fukushima Daiichi, the German Federal government decided that Germany will give up electricity generation from nuclear power within a decade. The last reactor will be disconnected from the power grid in 2022. Helping to make this opt-out safe is one of the duties of the Helmholtz Association with its Nuclear Safety Research Program within the Energy Research Area. Also the demolition of nuclear power plants and the repository problem will keep society, and thus also research, busy for a number of decades to come. Giving up electricity production from nuclear power thus must not mean giving up the required nuclear technology competences. In the fields of reactor safety, demolition, final storage, radiation protection, and crisis management, in critical support of international developments, and for competent evaluation of nuclear facilities around Germany, these competences will be in demand far beyond the German opt-out. This is the reason why the final report by the Ethics Committee on 'Safe Energy Supply' emphasizes the importance of nuclear technology research. Close cooperation on national, European and international levels is indispensable in this effort. Also nuclear safety research in the Helmholtz Association is aligned with the challenges posed by the opt-out of the use of nuclear power. It is important that the high competences in the areas of plant safety and demolition, handling of radioactive waste, and safe final storage as well as radiation protection be preserved. The Nuclear Safety Research Program within the Energy Research Area of the Helmholtz Association therefore will continue studying scientific and technical aspects of the safety of nuclear reactors and the safety of nuclear waste management. These research activities are provident research conducted for society and must be preserved for a long period of time. The work is closely harmonized with the activities of the partners in the

Thailand's nuclear research centre

International Nuclear Information System (INIS)

Yamkate, P.

2001-01-01

The Office of Atomic Energy for Peace, Thailand, is charged with three main tasks, namely, Nuclear Energy development Plan, Utilization of Nuclear Based technology Plan and Science and Technology Plan. Its activities are centred around the research reactor TRR-1/M1. The main areas of contribution include improvement in agricultural production, nuclear medicine and nuclear oncology, health care and nutrition, increasing industrial productivity and efficiency and, development of cadre competent in nuclear science and technology. The office also has the responsibility of ensuring nuclear safety, radiation safety and nuclear waste management. The office has started a new project in 1997 under which a 10 MWt research reactor, an isotope production facility and a waste processing and storage facility would be set up by General Atomic of USA. OAEP has a strong linkage with the IAEA and has been an active participant in RCA programmes. In the future OAEP will enhance its present capabilities in the use of radioisotopes and radiation and look into the possibility of using nuclear energy as an alternative energy resource. (author)

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.

Computational Design of Advanced Nuclear Fuels

International Nuclear Information System (INIS)

Savrasov, Sergey; Kotliar, Gabriel; Haule, Kristjan

2014-01-01

The objective of the project was to develop a method for theoretical understanding of nuclear fuel materials whose physical and thermophysical properties can be predicted from first principles using a novel dynamical mean field method for electronic structure calculations. We concentrated our study on uranium, plutonium, their oxides, nitrides, carbides, as well as some rare earth materials whose 4f eletrons provide a simplified framework for understanding complex behavior of the f electrons. We addressed the issues connected to the electronic structure, lattice instabilities, phonon and magnon dynamics as well as thermal conductivity. This allowed us to evaluate characteristics of advanced nuclear fuel systems using computer based simulations and avoid costly experiments.

Research on improvement of marine nuclear reactors and future perspective

International Nuclear Information System (INIS)

Yokomura, Takeyoshi

1988-01-01

The features when atomic energy is utilized on the sea are that the fuel cost is low, accordingly it is suitable to the power sources of large output, that the volume and weight of fuel are small, accordingly it is suitable to the continuous operation for a long period without refueling, and that oxygen is not required for the burning, accordingly it is suitable to undersea power sources. In USSR, four nuclear icebreakers have been in use, and four more are under construction. A nuclear LASH ship has been operated, and one more is under construction. As the other fields than sea transportation, an electricity generation barge MH-1A of USA used as the auxiliary power source for the Panama Canal and a research submarine NR-1 of USA have been in practical use. With the advance of ocean development in future, the creation of needs such as deep sea power stations, deep sea research ships and deep sea work ships is expected. Marine nuclear reactor technology was begun in the form of the nuclearization of merchant ships, and Savannah of USA, Otto Hahn of West Germany and Mutsu of Japan were built. The marine nuclear reactors built so far and of which the conceptual design was carried out are shown. The improvement of marine reactors is the reduction of size and weight, the simplification of the system, the adoption of self pressurization and self compensation and so on. The research on the improvement in Japan Atomic Energy Research Institute is reported. (Kako, I.)

Development of a Fissile Materials Irradiation Capability for Advanced Fuel Testing at the MIT Research Reactor

International Nuclear Information System (INIS)

Hu Linwen; Bernard, John A.; Hejzlar, Pavel; Kohse, Gordon

2005-01-01

A fissile materials irradiation capability has been developed at the Massachusetts Institute of Technology (MIT) Research Reactor (MITR) to support nuclear engineering studies in the area of advanced fuels. The focus of the expected research is to investigate the basic properties of advanced nuclear fuels using small aggregates of fissile material. As such, this program is intended to complement the ongoing fuel evaluation programs at test reactors. Candidates for study at the MITR include vibration-packed annular fuel for light water reactors and microparticle fuels for high-temperature gas reactors. Technical considerations that pertain to the design of the MITR facility are enumerated including those specified by 10 CFR 50 concerning the definition of a research reactor and those contained in a separate license amendment that was issued by the U.S. Nuclear Regulatory Commission to MIT for these types of experiments. The former includes limits on the cross-sectional area of the experiment, the physical form of the irradiated material, and the removal of heat. The latter addresses experiment reactivity worth, thermal-hydraulic considerations, avoidance of fission product release, and experiment specific temperature scrams

International topical meeting on nuclear research applications and utilization of accelerators. Book of abstracts

International Nuclear Information System (INIS)

2009-01-01

Applications of particle accelerators cover a number of areas, from strategic and applied research, safety and security, environmental applications, materials research and analytical sciences, to radioisotope production and radiation processing. Accelerator based techniques and pulsed neutron sources are expected to lead to new initiatives in materials research of relevance for both the nuclear and non-nuclear fields. Material science studies with the use of accelerators, neutron beams and other nuclear analytical methods are relevant to the development of advanced reactors, nuclear fuel cycle needs and fusion research. In this regard, a better understanding of the irradiation effects in materials for energy and non-energy applications is needed, and is reflected in accelerator techniques for modification and analysis of materials for nuclear technologies. Accelerator applications for innovative nuclear systems aiming at rad-waste transmutation (e.g., accelerator driven systems) are being pursued in many countries. Research and development using accelerators involves a broad spectrum of skills to build a cadre of trained experts in nuclear techniques in IAEA Member States, and to generate knowledge for innovative methodologies and tools. The present conference is also being held in cooperation with the American Nuclear Society (ANS), which successfully organized the series of accelerator applications conferences known as AccApp. The ANS series of topical meetings has provided a forum for the global exchange of scientific and technical knowledge on a wide variety of related topics since the first AccApp took place in 1997 in Albuquerque, USA. The last conference which was held in 2007 in Pocatello, USA, was jointly organized by the ANS and the IAEA. The main objectives of the conference are to promote exchange of information among IAEA Member States representatives/delegates and to discuss new trends in accelerator applications including nuclear materials research

Outline of results of safety research (in nuclear fuel cycle field in fiscal year 1996)

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-01

The safety research in Power Reactor and Nuclear Fuel Development Corporation in fiscal year 1996 has been carried out based on the basic plan of safety research (from fiscal year 1996 to 2000) which was decided in March, 1996. In this report, on nuclear fuel cycle field, namely all the subjects in the fields of nuclear fuel facilities, environmental radioactivity and waste disposal, and the subjects related to nuclear fuel facilities among the fields of aseismatic and probabilistic safety assessments, the results of research in fiscal year 1996, the first year of the 5-year project, are summarized together with the outline of the basic plan of safety research. The basic policy, objective and system for promotion of the safety research are described. The objectives of the safety research are the advancement of safety technology, the safety of facilities, stable operation techniques, the safety design and the evaluation techniques of next generation facilities, and the support of transferring nuclear fuel cycle to private businesses. The objects of the research are uranium enrichment, fuel fabrication and reprocessing, and waste treatment and storage. 52 investigation papers of the results of the safety research in nuclear fuel cycle field in fiscal year 1996 are collected in this report. (K.I.)

Experimental nuclear physics research in Hungary

International Nuclear Information System (INIS)

Koltay, Ede.

1984-01-01

The status and recent results of experimental nuclear physics in Hungary is reviewed. The basic nuclear sciences, instrumental background and international cooperation are discussed. Personal problems and the effects of the international scientific deconjuncture are described. The applied nuclear and interdisciplinary researches play an important role in Hungarian nuclear physics. Some problems of cooperation of Hungarian nuclear and other research institutes applying or producing nuclear analytical technology are reviewed. The new instrument, the Debrecen cyclotron under construction gives new possibilities to basic and applied researches. A new field of Hungarian nuclear physics is the fusion and plasma research using tokamak equipment, the main topics of which are plasma diagnostics and fusion control systems. Some practical applications of Hungarian nuclear physical results, e.g. establishment of new analytical techniques like PIXE, RBS, PIGE, ESCA, etc. are summarized. (D.Gy.)

Karlsruhe Nuclear Research Center. Research and development program 1991

International Nuclear Information System (INIS)

1990-01-01

The R and D activities of the KfK are classified in 8 main research activities: 1) project nuclear fusion; 2) project pollutant mitigation in the environment; 3) solid state and materials research; 4) nuclear and elementary particle physics; 5) microtechnics e.g. X-ray lithography; 6) materials handling; 7) project nuclear safety research; 8) radioactive waste management. (orig.) [de

Nanomaterials and nanotechnologies in nuclear energy chemistry

International Nuclear Information System (INIS)

Shi, W.Q.; Yuan, L.Y.; Li, Z.J.; Lan, J.H.; Zhao, Y.L.; Chai, Z.F.

2012-01-01

With the rapid growth of human demands for nuclear energy and in response to the challenges of nuclear energy development, the world's major nuclear countries have started research and development work on advanced nuclear energy systems in which new materials and new technologies are considered to play important roles. Nanomaterials and nanotechnologies, which have gained extensive attention in recent years, have shown a wide range of application potentials in future nuclear energy system. In this review, the basic research progress in nanomaterials and nanotechnologies for advanced nuclear fuel fabrication, spent nuclear fuel reprocessing, nuclear waste disposal and nuclear environmental remediation is selectively highlighted, with the emphasis on Chinese research achievements. In addition, the challenges and opportunities of nanomaterials and nanotechnologies in future advanced nuclear energy system are also discussed. (orig.)

Nuclear methods in environmental and energy research

Energy Technology Data Exchange (ETDEWEB)

Vogt, J. R. [ed.

1977-01-01

The topics considered in the seven sessions were nuclear methods in atmospheric research; nuclear and atomic methodology; nuclear methods in tracer applications; energy exploration, production, and utilization; nuclear methods in environmental monitoring; nuclear methods in water research; and nuclear methods in biological research. Individual abstracts were prepared for each paper. (JSR)

International cooperation in advanced nuclear systems. An option for the future

International Nuclear Information System (INIS)

Dee, J.B.; Kupitz, J.; O'Hara, F.

1986-10-01

Long-term energy problems are shared by all countries through world trade, and only a global solution can alleviate the anticipated future energy supply shortages for all. The only non-polluting, technologically-proven future energy supply options are offered by advanced nuclear power systems that utilize uranium and thorium as fertile fuel materials. For this reason, every major country with a nuclear power industry has a development programme for fast breeder and/or advanced converter nuclear power reactors. In these programmes international ventures have become the rule rather that the exception. The development of special district heating reactor systems is progressing as a CMEA collaboration. In the field of fast breeder reactors such ventures include the SNR-300, the FBTF, the Superphenix, and also the commercialization programmes BN-800/1600 (COMECON) and the Superphenix-II (ARGO group). The basic objective of the IAEA is to enlarge the contribution of atomic energy to peace, health and prosperity around the world. For those Member States with development programmes the Agency promotes status and planning, to share experience on prototype plant operation, and to cooperate in identifying critical development issues. For Member States without major programmes, the Agency compiles authoritative and objective world-wide plant data, publishes reports on world-wide development status, coordinates small exploratory research programmes and provides technical assistance through expert services and equipment procurement. By providing the only existing global forum for promoting East-West and North-South inter-communication these IAEA activities encourage cooperation between countries engaged in development and inform countries interested to know more about the role of advanced reactors for meeting their future energy needs, which will become today's energy needs in the not-too-distant future

Training related research and development conducted at Oak Ridge National Laboratory for the US Nuclear Regulatory Commission

International Nuclear Information System (INIS)

Haas, P.M.

1985-01-01

For a number of years Oak Ridge National Laboratory (ORNL) has conducted a sizeable program of human factors research and development in support of the Office of Nuclear Regulatory Research of the US Nuclear Regulatory Commission (NRC). The history of this effort has in many ways paralleled the growth of human factors R and D throughout the nuclear industry and the program has contributed to advances in the industry as well as to NRC regulatory and research programs. This paper reviews the major projects and products of the program relevant to training and concludes with an identification of future R and D needs

Nuclear data and low energy nuclear research in Israel

International Nuclear Information System (INIS)

Yiftah, S.

1977-04-01

The Israel Nuclear Data and Low Energy Nuclear Research relevant to the International Nuclear Data Committee was continued in various institutions. The major experimental facilities consist of: A 5 Megawatt swimming pool enriched uranium reactor at the Soreq Nuclear Research Centre; A 26 Megawatt heavy water tank-type natural uranium reactor at the Negev Research Centre; A 6-million volt EN tandem accelerator at the Weizmann Institute of Science, Rehovot; The new most modern high energy 14 UD pelletron accelerator manufactured by the National Electrostatic Corporation of Middleton, Wisconsin, installed inside the Koffler Accelerator Tower at the Weizmann Institute of Science, Rehovot. Brief abstracts of the research work, both published and unpublished, listed according to the various laboratories, are reported in the following pages. (author)

Research on Elemental Technology of Advanced Nuclear Fuel Performance Verification

International Nuclear Information System (INIS)

Kim, Yong Soo; Lee, Dong Uk; Jean, Sang Hwan; Koo, Min

2003-04-01

Most of current properties models and fuel performance models used in the performance evaluation codes are based on the in-pile data up to 33,000 MWd/MtU. Therefore, international experts are investigating the properties changes and developing advanced prediction models for high burn-up application. Current research is to develop high burn-up fission gas release model for the code and to support the code development activities by collecting data and models, reviewing/assessing the data and models together, and benchmarking the selected models against the appropriate in-pile data. For high burn-up applications, two stage two step fission gas release model is developed based on the real two diffusion process in the grain lattice and grain boundaries of the fission gases and the observation of accelerated release rate in the high burn-up. It is found that the prediction of this model is in excellent agreement with the in-pile measurement results, not only in the low burn-up but also in the high burn-up. This research is found that the importance of thermal conductivity of oxide fuel, especially in the high burn-up, is focused again. It is found that even the temperature dependent models differ from one to another and most of them overestimate the conductivity in the high burn-up. An in-pile data benchmarking of high LHGR fuel rod shows that the difference can reach 30%∼40%, which predicts 400 .deg. C lower than the real fuel centerline temperature. Recent models on the thermal expansion and heat capacity of oxide fuel are found to be well-defined. Irradiation swelling of the oxide fuel are now well-understood that in most cases in LWRs solid fission product swelling is dominant. Thus, the accumulation of in-pile data can enhance the accuracy of the model prediction, rather than theoretical modeling works. Thermo-physical properties of Zircaloy cladding are also well-defined and well-understood except the thermal expansion. However, it turns out that even the

Advanced I and C systems for nuclear power plants feedback of experience

International Nuclear Information System (INIS)

Prehler, H.J.

2001-01-01

Advanced I and C systems for nuclear power plants have to meet increasing demands for safety and availability. Additionally specific requirements arising from nuclear qualification have to be fulfilled. To meet both subjects adequately in the future, Siemens has developed advanced I and C technology consisting of the two complementary I and C systems TELEPERM XP and TELEPERM XS.(author)

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)

Current Research on Containment Technologies for Verification Activities: Advanced Tools for Maintaining Continuity of Knowledge

International Nuclear Information System (INIS)

Smartt, H.; Kuhn, M.; Krementz, D.

2015-01-01

The U.S. National Nuclear Security Administration (NNSA) Office of Non-proliferation and Verification Research and Development currently funds research on advanced containment technologies to support Continuity of Knowledge (CoK) objectives for verification regimes. One effort in this area is the Advanced Tools for Maintaining Continuity of Knowledge (ATCK) project. Recognizing that CoK assurances must withstand potential threats from sophisticated adversaries, and that containment options must therefore keep pace with technology advances, the NNSA research and development on advanced containment tools is an important investment. The two ATCK efforts underway at present address the technical containment requirements for securing access points (loop seals) and protecting defined volumes. Multiple U.S. national laboratories are supporting this project: Sandia National Laboratories (SNL), Savannah River National Laboratory (SRNL), and Oak Ridge National Laboratory (ORNL). SNL and SRNL are developing the ''Ceramic Seal,'' an active loop seal that integrates multiple advanced security capabilities and improved efficiency housed within a small-volume ceramic body. The development includes an associated handheld reader and interface software. Currently at the prototype stage, the Ceramic Seal will undergo a series of tests to determine operational readiness. It will be field tested in a representative verification trial in 2016. ORNL is developing the Whole Volume Containment Seal (WCS), a flexible conductive fabric capable of enclosing various sizes and shapes of monitored items. The WCS includes a distributed impedance measurement system for imaging the fabric surface area and passive tamper-indicating features such as permanent-staining conductive ink. With the expected technology advances from the Ceramic Seal and WCS, the ATCK project takes significant steps in advancing containment technologies to help maintain CoK for various verification

Advanced high brightness ion rf accelerator applications in the nuclear energy

International Nuclear Information System (INIS)

Jameson, R.A.

1991-01-01

The capability of modern rf linear accelerators to provide intense high quality beams of protons, deuterons, or heavier ions is opening new possibilities for transmuting existing nuclear wastes, for generating electricity from readily available fuels with minimal residual wastes, for building intense neutron sources for materials research, for inertial confinement fusion using heavy ions, and for other new applications. These are briefly described, couched in a perspective of the advances in the understanding of the high brightness beams that has enabled these new programs. 32 refs., 2 figs

The advanced neutron source research and development plan

International Nuclear Information System (INIS)

Selby, D.L.

1995-08-01

The Advanced Neutron Source (ANS) is being designed as a user-oriented neutron research laboratory centered around the most intense continuous beams of thermal and subthermal neutrons in the world (an order of magnitude more intense than beams available from the most advanced existing reactors). The ANS will be built around a new research reactor of 330-MW fission power, producing an unprecedented peak thermal flux of >7 · 10 19 · m -2 · s -1 . Primarily a research facility, the ANS will accommodate more than 1000 academic, industrial, and government researchers each year. They will conduct basic research in all branches of science as well as applied research leading to better understanding of new materials, including high temperature super conductors, plastics, and thin films. Some 48 neutron beam stations will be set up in the ANS beam rooms and the neutron guide hall for neutron scattering and for fundamental and nuclear physics research. There also will be extensive facilities for materials irradiation, isotope production, and analytical chemistry. The top level work breakdown structure (WBS) for the project. As noted in this figure, one component of the project is a research and development (R ampersand D) program (WBS 1.1). This program interfaces with all of the other project level two WBS activities. Because one of the project guidelines is to meet minimum performance goals without relying on new inventions, this R ampersand D activity is not intended to produce new concepts to allow the project to meet minimum performance goals. Instead, the R ampersand D program will focus on the four objectives described

Nuclear heat source design for an advanced HTGR process heat plant

International Nuclear Information System (INIS)

McDonald, C.F.; O'Hanlon, T.W.

1983-01-01

A high-temperature gas-cooled reactor (HTGR) coupled with a chemical process facility could produce synthetic fuels (i.e., oil, gasoline, aviation fuel, methanol, hydrogen, etc.) in the long term using low-grade carbon sources (e.g., coal, oil shale, etc.). The ultimate high-temperature capability of an advanced HTGR variant is being studied for nuclear process heat. This paper discusses a process heat plant with a 2240-MW(t) nuclear heat source, a reactor outlet temperature of 950 0 C, and a direct reforming process. The nuclear heat source outputs principally hydrogen-rich synthesis gas that can be used as a feedstock for synthetic fuel production. This paper emphasizes the design of the nuclear heat source and discusses the major components and a deployment strategy to realize an advanced HTGR process heat plant concept

Objectives for the development of advanced nuclear plants

International Nuclear Information System (INIS)

1993-01-01

The scope of this report is to reiterate the broad objectives for the development of advanced nuclear plants, to set forth some related subobjectives and to propose some universal goals for the development programmes. The majority of these can be categorized under the headings of enhancing safety, improving reliability and gaining better economics. These categories are used in the report followed by additional categories considered to be important within the global framework intended. Additional broad objectives appear unlikely but more subobjectives may become evident as time progresses and the need arises to express them in the intended more global framework. The goals also may change. The scope is therefore a set of objectives for development of advanced nuclear plants. The objectives are believed to be universally acceptable; they have been reviewed on that basis. 13 refs

Argonne National Laboratory: An example of a US nuclear research centre

International Nuclear Information System (INIS)

Bhattacharyya, S.

2001-01-01

The nuclear era was ushered in 1942 with the demonstration of a sustained nuclear chain reaction in Chicago Pile 1 facility. The USA then set up five large national multi disciplinary laboratories for developing nuclear technology for civilian use and three national laboratories for military applications. Reactor development, including prototype construction, was the main focus of the Argonne National Laboratory. More than 100 power reactors operating in the USA have benefited from R and D in the national laboratories. However, currently the support for nuclear power has waned. With the end of the cold war there has also been a need to change the mission of laboratories involved in military applications. For all laboratories of the Department of Energy (DOE) the mission, which was clearly focused earlier on high risk, high payoff long term R and D has now become quite diffused with a number of near term programmes. Cost and mission considerations have resulted in shutting down of many large facilities as well as auxiliary facilities. Erosion of infrastructure has also resulted in reduced opportunities for research which means dwindling of interest in nuclear science and engineering among the younger generation. The current focus of nuclear R and D in the DOE laboratories is on plant life extension, deactivation and decommissioning, spent fuel management and waste management. Advanced aspects include space nuclear applications and nuclear fusion R and D. At the Argonne National Laboratory, major initiatives for the future would be in the areas of science, energy, environment and non-proliferation technologies. International collaboration would be useful mechanisms to achieve cost effective solutions for major developmental areas. These include reactor operation and safety, repositories for high level nuclear waste, reactor system decommissioning, large projects like a nuclear fusion reactor and advanced power reactors. The IAEA could have a positive role in these

Review of research on advanced computational science in FY2015

International Nuclear Information System (INIS)

2017-01-01

Research on advanced computational science for nuclear applications, based on 'Plan to Achieve Medium- to Long-term Objectives of the Japan Atomic Energy Agency (Medium- to Long-term Plan)', has been performed at Center for Computational Science and e-Systems (CCSE), Japan Atomic Energy Agency. CCSE established the committee consisting of outside experts and authorities which does research evaluation and advices for the assistance of the research and development. This report summarizes the followings. (1) Results of the R and D performed at CCSE in FY 2015 (April 1st, 2015 - March 31st, 2016), (2) Results of the evaluation on the R and D by the committee in FY 2015 (April 1st, 2015 - March 31st, 2016). (author)

Annual report of Nuclear Engineering Research Laboratory, University of Tokyo in fiscal 1990

International Nuclear Information System (INIS)

1991-01-01

In this annual report, the activities of research and education and the state of operation of the research facilities in this Laboratory in fiscal year 1990 are summarized. There are four large research facilities in this Laboratory, that is, the fast neutron source reactor 'Yayoi', the electron beam linear accelerator, the nuclear fusion reactor blanket experiment device and the heavy ion irradiation research facility. Those are used to execute research and education in the wide fields of atomic energy engineering, and put to the common utilization by universities in whole Japan. The results of the research with these facilities have been reported in the separate reports. The research aims at developing the most advanced and new fields in nuclear reactor engineering, and includes the engineering of the first wall and the fuel cycle for nuclear fusion reactors, electromagnetic structure engineering, AI and robotics, quantum beam engineering, the design of new type reactors, the basic process of radiochemistry and so on. The report on the course of the large scale facilities, research activities, the publication of research, education and the events in the Laboratory in the year are described. (K.I.)

The technological study on the decommissioning of nuclear facility, etc. in the Tokai Research Establishment

International Nuclear Information System (INIS)

Tomii, Hiroyuki; Matsuo, Kiyoshi; Shiraishi, Kunio; Kato, Rokuro; Watabe, Kozou; Higashiyama, Yutaka; Nagane, Satoru

2005-03-01

Since JPDR is dismantled and is removed, in Tokai Research Establishment, Japan Atomic Energy Research Institute, the dismantling of nuclear facility which finished the mission, etc. is advanced. At present, nuclear facility as a dismantling object count the approximately 20 facilities, and decommissioning plan of these facilities becomes an important problem, when the decommissioning countermeasure is considered. However, decommissioning techniques in proportion to various nuclear facility, etc. are clearly, and it has not been determined. In this report, the technical consideration on decommissioning techniques of nuclear facility promoted on the basis of this experience in future, while until now decommissioning experience and technical knowledge are arranged, etc. was added in order to appropriately and surely carry out decommissioning techniques and legal procedures, etc. (author)

Human factors design review guidelines for advanced nuclear control room technologies

International Nuclear Information System (INIS)

O'Hara, J.; Brown, W.; Granda, T.; Baker, C.

1991-01-01

Advanced control rooms (ACRs) for future nuclear power plants are being designed utilizing computer-based technologies. The US Nuclear Regulatory Commission reviews the human engineering aspects of such control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported in order to protect public health and safety. This paper describes the rationale, general approach, and initial development of an NRC Advanced Control Room Design Review Guideline. 20 refs., 1 fig

Research on advancement of method for evaluating aseismatic ability of rock discontinuity plane in ground and surrounding slopes of nuclear power facilities

International Nuclear Information System (INIS)

Kusunose, Kinichiro; Cho, Akio; Takahashi, Manabu; Kamai, Toshitaka

1997-01-01

The purpose of this research is to carry out the technical development required for exploring with high accuracy the distribution and shapes of the discontinuity planes in rocks in the ground and surrounding cut-off slopes of nuclear power facilities, and to advance the techniques of interpreting and evaluating quantitatively the stability against earthquakes of the discontinuity planes. This research consists of two themes: the research on the method of investigating the three-dimensional distribution of the crevices in the ground and the research on the method of evaluating the aseismatic ability in the slopes. As for the first theme, one of the techniques for exploring underground structure with elastic waves, tomography, is explained, and the development of the 12 channel receiver and the program for the multi-channel analysis and processing of waveform are reported. As for the second theme, the stability analysis was carried out on three actual cases of landslide. The equation for stability analysis is shown, and the results are reported. The strength at the time of forming separation plane gives the most proper result. (K.I.)

Selection and development of advanced nuclear fuel products

International Nuclear Information System (INIS)

Stucker, David L.; Miller, Richard S.; Arnsberger, Peter L.

2004-01-01

The highly competitive international marketplace requires a continuing product development commitment, short development cycle times and timely, on-target product development to assure customer satisfaction and continuing business. Westinghouse has maintained its leadership position within the nuclear fuel industry with continuous developments and improvements to fuel assembly materials and design. This paper presents a discussion of the processes used by Westinghouse in the selection and refinement of advanced concepts for deployment in the highly competitive US and international nuclear fuel fabrication marketplace. (author)

Nuclear research center transformation experience

International Nuclear Information System (INIS)

Diaz, J. L.; Jimenez, J. M.

2001-01-01

As consequence of the changes in the energy polities of each countries in the 80th. many of the Nuclear Research Centres suffered a transformation (more of less deep) in other Research and Development Centres with a wider spectrum that the exclusively nuclear one. This year is the 50 anniversary of the Spanish Centre of Nuclear Research-Junta de Energia Nuclear.The JEN the same as other suffered a deep renovation to become the CIEMAT Centro de Investigaciones Energeticas Medioambientales y Tecnologicas (Research Centre for Energy, Environment and Technology). This paper is focussed on the evolution of JEN to CIEMAT besides analysing the reach of this re-foundation considering the political reasons and technical aspect that justified it and the laws in those it is based on. (Author)

Progress of nuclear safety research, (1)

International Nuclear Information System (INIS)

Amano, Hiroshi; Nakamura, Hiroei; Nozawa, Masao

1981-01-01

The Japan Atomic Energy Research Institute was established in 1956 in conformity with the national policy to extensively conduct the research associated with nuclear energy. Since then, the research on nuclear energy safety has been conducted. In 1978, the Division of Reactor Safety was organized to conduct the large research programs with large scale test facilities. Thereafter, the Divisions of Reactor Safety Evaluation, Environmental Safety Research and Reactor Fuel Examination were organized successively in the Reactor Safety Research Center. The subjects of research have ranged from the safety of nuclear reactors to that in the recycling of nuclear fuel. In this pamphlet, the activities in JAERI associated with the safety research are reported, which have been carried out in the past two years. Also, the international cooperation research program in which JAERI participated is included. This pamphlet consists of two parts, and in this Part 1, the reactor safety research is described. The safety of nuclear fuel, the integrity and safety of pressure boundary components, the engineered safety in LOCA, fuel behavior in accident and others are reported. (Kako, I.)

Advanced passive technology: A global standard for nuclear plant requirements

International Nuclear Information System (INIS)

Novak, V.

1994-01-01

Since 1984, Westinghouse has been developing AP8OO, a 800 MW, two-loop advanced passive plant, in response to an initiative established by the Electric Power Research Institute (EPRI) and the U.S. Department of Energy' (DOE). The preliminary design was cornpleved in 1989. AP6OO's Standard Safety Analysis and Probabilistic Risk analysis Reports were submitted to the U.S. Nuclear Regulatory Commission for design certification in 1992. Design simplification is the key strategy behind the AP6OO. The basic technical concept Of simplification has resulted in a simplified reactor coolant systems, simplified plant systems, a simplified plant arrangement, reduced number of components, simplified operation and maintenance

Advanced passive technology: A global standard for nuclear plant requirements

Energy Technology Data Exchange (ETDEWEB)

Novak, V

1994-12-31

Since 1984, Westinghouse has been developing AP8OO, a 800 MW, two-loop advanced passive plant, in response to an initiative established by the Electric Power Research Institute (EPRI) and the U.S. Department of Energy` (DOE). The preliminary design was cornpleved in 1989. AP6OO`s Standard Safety Analysis and Probabilistic Risk analysis Reports were submitted to the U.S. Nuclear Regulatory Commission for design certification in 1992. Design simplification is the key strategy behind the AP6OO. The basic technical concept Of simplification has resulted in a simplified reactor coolant systems, simplified plant systems, a simplified plant arrangement, reduced number of components, simplified operation and maintenance.

The European Community's research and development programme on the decommissioning of nuclear installations

International Nuclear Information System (INIS)

Skupinski, E.

1988-01-01

The Commission of the European Communities (CEC) continued with a second research programme on the decommissioning of nuclear installations (1984-88), after having completed a first programme on the decommissioning of nuclear power plants (1979-83). The programme, which has about 70 research contracts with organisations or private firms in the member states, includes the development and testing of advanced techniques, such as decontamination and dismantling, and the consideration of the radioactive waste arising therefrom. Work is done at laboratory scale or in the context of large-scale decommissioning operations. The paper will give an overview on the technical content and on some selected results. (author)

Cost estimate guidelines for advanced nuclear power technologies

International Nuclear Information System (INIS)

Hudson, C.R. II.

1986-07-01

To make comparative assessments of competing technologies, consistent ground rules must be applied when developing cost estimates. This document provides a uniform set of assumptions, ground rules, and requirements that can be used in developing cost estimates for advanced nuclear power technologies

Cost estimate guidelines for advanced nuclear power technologies

International Nuclear Information System (INIS)

Hudson, C.R. II.

1987-07-01

To make comparative assessments of competing technologies, consistent ground rules must be applied when developing cost estimates. This document provides a uniform set of assumptions, ground rules, and requirements that can be used in developing cost estimates for advanced nuclear power technologies

Advanced robot vision system for nuclear power plants

International Nuclear Information System (INIS)

Onoguchi, Kazunori; Kawamura, Atsuro; Nakayama, Ryoichi.

1991-01-01

We have developed a robot vision system for advanced robots used in nuclear power plants, under a contract with the Agency of Industrial Science and Technology of the Ministry of International Trade and Industry. This work is part of the large-scale 'advanced robot technology' project. The robot vision system consists of self-location measurement, obstacle detection, and object recognition subsystems, which are activated by a total control subsystem. This paper presents details of these subsystems and the experimental results obtained. (author)

The Russian nuclear data research programme

International Nuclear Information System (INIS)

1995-11-01

The report contains the Russian programme of nuclear data research, approved by the Russian Nuclear Data Committee on 16 December 1994. It gives surveys on nuclear data needs, on the structure of nuclear data activities, on experimental facilities for nuclear data measurements at five Russian institutes, on theoretical model work, nuclear data evaluation, and nuclear data testing. It describes four Russian nuclear data centers and their relations to the International Nuclear Data Centres Network, and their holdings of nuclear data libraries of Russian and international origin. A summary of nuclear data applications in energy and non-energy fields is given. An appendix contains a detail nuclear data research programme for the years 1995 - 2005. (author). 16 refs, 1 fig., 6 tabs

Nuclear generation cost and nuclear research development fund

International Nuclear Information System (INIS)

Kim, S. S.; Song, G. D.

2000-01-01

The main objective of this study is to analyze the effects of nuclear R and D fund to nuclear generation cost and to assess the adaptability of fund size through the comparison with the nuclear research fund in Japan. It was estimated that nuclear R and D fund increased the average annual unit cost of nuclear power generation by 1.14 won/kWh. When the size of nuclear R and D fund is compared with that in Japan, this study suggests that the current nuclear R and D fund should be largely increased taking into consideration the ratio of R and D fund to nuclear generation

Subsonic Ultra Green Aircraft Research Phase II: N+4 Advanced Concept Development

Science.gov (United States)

Bradley, Marty K.; Droney, Christopher K.

2012-01-01

This final report documents the work of the Boeing Subsonic Ultra Green Aircraft Research (SUGAR) team on Task 1 of the Phase II effort. The team consisted of Boeing Research and Technology, Boeing Commercial Airplanes, General Electric, and Georgia Tech. Using a quantitative workshop process, the following technologies, appropriate to aircraft operational in the N+4 2040 timeframe, were identified: Liquefied Natural Gas (LNG), Hydrogen, fuel cell hybrids, battery electric hybrids, Low Energy Nuclear (LENR), boundary layer ingestion propulsion (BLI), unducted fans and advanced propellers, and combinations. Technology development plans were developed.

International research and development projects in nuclear energy: Experience and future prospects

International Nuclear Information System (INIS)

Strohl, P.

1983-01-01

From the very beginning nuclear energy appeared as a fruitful field for international co-operation and particularly for international projects and joint ventures. By pooling scientific, technical and financial resources, the participating countries sought to promote the development of technology and the transition of nuclear energy to the industrial stage. Governments and therefore intergovernmental organizations were the driving force behind the establishment of joint projects in various R and D sectors, often in association with industry and private research institutes. The situation changed considerably from the end of the 1960s onwards. Despite some remarkable technical achievements, international co-operation did not develop to the extent predicted at the outset. Industry took over in the exploitation of proven technologies, and industrial co-operation agreements have become an important feature in some key areas of nuclear energy. This trend raises questions as to the future of joint R and D projects organized through intergovernmental co-operation. Although such projects are still very useful, they tend to be concentrated in those few sectors which continue to be of direct interest to the Governments; for instance, fundamental research, radioactive waste management and nuclear safety. The position of nuclear energy has changed, and the benefits to be drawn from this form of international co-operation must be critically re-assessed accordingly. While advantage to be gained from international projects for countries which are the most advanced in the development of nuclear energy is not the same as it was at the beginning, the transfer of experience and knowledge to less advanced countries is still the main concern of projects dealing with safety and regulatory matters. The experience thus gained provides a very useful insight into the legal and institutional framework of joint projects

Study on operation conditions and an operation system of a nuclear powered submersible research vessel, 'report of working group on application of a very small nuclear reactor to an ocean research'

International Nuclear Information System (INIS)

Ura, Tamaki; Takamasa, Tomoji; Nishimura, Hajime

2001-07-01

JAERI has studied on design of a nuclear powered submersible research vessel, which will navigate under sea mainly in the Arctic Ocean, as a part of the design activity of advanced marine reactors. This report describes operation conditions and an operating system of the vessel, which were discussed by the specialists of hull design, sound positioning, ship motions and oceanography, etc. The design conditions on ship motions for submersible vessels were surveyed considering regulations in our country, and ship motions were evaluated in the cases of underwater and surface navigations taking account of observation activities in the Arctic Ocean. The effect of ship motions on the compact nuclear reactor SCR was assessed. A submarine transponder system and an on-ice communication buoy system were examined as a positioning and communication system, supposing the activity under ice. The interval between transponders or communication buoys was recommended as 130 km. Procedures to secure safety of nuclear powered submersible research vessel were discussed according to accidents on the hull or the nuclear reactor. These results were reflected to the concept of the nuclear powered submersible research vessel, and subjects to be settled in the next step were clarified. (author)

Advanced nuclear reactor public opinion project. Interim report

Energy Technology Data Exchange (ETDEWEB)

Benson, B.

1991-07-25

This Interim Report summarizes the findings of our first twenty in-depth interviews in the Advanced Nuclear Reactor Public Opinion Project. We interviewed 6 industry trade association officials, 3 industry attorneys, 6 environmentalists/nuclear critics, 3 state officials, and 3 independent analysts. In addition, we have had numerous shorter discussions with various individuals concerned about nuclear power. The report is organized into the four categories proposed at our April, 1991, Advisory Group meeting: safety, cost-benefit analysis, science education, and communications. Within each category, some change of focus from that of the Advisory Group has been required, to reflect the findings of our interviews. This report limits itself to describing our findings. An accompanying memo draws some tentative conclusions.

Research for nuclear power. A Swiss perspective

International Nuclear Information System (INIS)

Foskolos, K.; Yadigaroglu, G.; Chawla, R.; Paul Scherrer Inst., Villigen

1996-01-01

Nuclear energy research in Switzerland is concentrated in the Department for Nuclear Energy and Safety Research of the Paul Scherrer Institute (PSI). Nuclear research at PSI is structured around three main poles: safety and related operational issues for existing NPPs, nuclear waste management, and safety characteristics of future reactor concepts. Further, global aspects of energy systems are examined with regard to safety, economics and environmental impact. Presently, a total effort of about 200 py/a is invested in the nuclear research. Government funding of nuclear research was relatively stable during recent years, reaching about 35 MCHF/a. External funding of about 15 MCHF/a is expected to remain stable. (R.P.)

An overview of nuclear physics research

International Nuclear Information System (INIS)

Kapoor, S.S.

2010-01-01

This overview is aimed to give a general picture of the global developments in nuclear physics research over the years since the beginning. It is based on the inaugural talk given at the 54th annual nuclear physics symposium organized by the Department of Atomic Energy, which was held as an International Symposium at BARC, Mumbai during Dec 8-12, 2009. The topics of nuclear fission, nuclear shell effects, super-heavy nuclei, and expanding frontiers of nuclear physics research with the medium to ultra-relativistic energy heavy-ion reactions are in particular highlighted. Accelerator driven sub-critical reactor system (ADS) is briefly described in the end as an example of spin-off of nuclear physics research. (author)

NuclearFACTS: public engagement about the impacts of nuclear research

Energy Technology Data Exchange (ETDEWEB)

Dalzell, M.T.J.; Alexander, R.N.; Main, M.G., E-mail: matthew.dalzell@fedorukcentre.ca [Sylvia Fedoruk Canadian Centre for Nuclear Innovation, Saskatoon, SK, (Canada)

2015-07-01

The Forum for Accountability and Communities Talking nuclear Science - nuclearFACTS - is a cornerstone of the Sylvia Fedoruk Canadian Centre for Nuclear Innovation's efforts to engage the people of Saskatchewan in evidence-based conversations about the impacts of the nuclear research, development and training activities supported by the Fedoruk Centre. The second annual nuclearFACTS public colloquium was held 20 November 2014, and featured the participation of 16 research projects. This paper discusses the continued development of the nuclearFACTS concept and its role in the Fedoruk Centre's upstream engagement efforts. (author)

Local AREA networks in advanced nuclear reactors

International Nuclear Information System (INIS)

Bicknell, J.; Keats, A.B.

1984-01-01

The report assesses Local Area Network Communications with a view to their application in advanced nuclear reactor control and protection systems. Attention is focussed on commercially available techniques and systems for achieving the high reliability and availability required. A basis for evaluating network characteristics in terms of broadband or baseband type, medium, topology, node structure and access method is established. The reliability and availability of networks is then discussed. Several commercial networks are briefly assessed and a distinction made between general purpose networks and those suitable for process control. The communications requirements of nuclear reactor control and protection systems are compared with the facilities provided by current technology

Advancing materials research

International Nuclear Information System (INIS)

Langford, H.D.; Psaras, P.A.

1987-01-01

The topics discussed in this volume include historical perspectives in the fields of materials research and development, the status of selected scientific and technical areas, and current topics in materials research. Papers are presentd on progress and prospects in metallurgical research, microstructure and mechanical properties of metals, condensed-matter physics and materials research, quasi-periodic crystals, and new and artifically structured electronic and magnetic materials. Consideration is also given to materials research in catalysis, advanced ceramics, organic polymers, new ways of looking at surfaces, and materials synthesis and processing

Main research results in the field of nuclear power engineering of the Nuclear Reactors and Thermal Physics Institute in 2014

International Nuclear Information System (INIS)

Trufanov, A.A.; Orlov, Yu.I.; Sorokin, A.P.; Chernonog, V.L.

2015-01-01

The main results of scientific and technological activities for last years of the Nuclear Reactors and Thermal Physics Institute FSUE SSC RF - IPPE in solving problems of nuclear power engineering are presented. The work have been carried out on the following problems: justification of research and development solutions and safety of NPPs with fast reactors of new generation with sodium (BN-1200, MBIR) and lead (BREST-OD-300) coolants, justification of safety of operating and advanced NPPs with WWER reactor facilities (WWER-1000, AEhS 2006, WWER-TOI), development and benchmarking of computational codes, research and development support of Beloyarsk-3 (BN-600) and Bilibino (BN-800) NPPs operation, decommissioning of AM and BR-10 research reactors, pilot scientific studies (WWER-SKD, ITER), international scientific and technical cooperation. Problems for further investigations are charted [ru

Cost-estimate guidelines for advanced nuclear power technologies

International Nuclear Information System (INIS)

Delene, J.G.; Hudson, C.R.

1993-01-01

Various advanced power plant concepts are currently under development. These include several advanced light water reactors as well as the modular high-temperature gas-cooled reactor and the advanced liquid-metal reactor. One measure-of the attractiveness of a new concept is cost. Invariably, the cost of a new type of power plant will be compared with other alternative forms of electric generation. In order to make reasonable comparative assessments of competing technologies, consistent ground rules and assumptions must be applied when developing cost estimates. This paper describes the cost-estimate guidelines developed by Oak Ridge National Laboratory for the U.S. Department of Energy (DOE) to be used in developing cost estimates for the advanced nuclear reactors and how these guidelines relate to the DOE cost verification process

Intermediate/Advanced Research Design and Statistics

Science.gov (United States)

Ploutz-Snyder, Robert

2009-01-01

The purpose of this module is To provide Institutional Researchers (IRs) with an understanding of the principles of advanced research design and the intermediate/advanced statistical procedures consistent with such designs

Researches on nuclear wastes. Knowledge gained and perspectives at the 2006 date line

International Nuclear Information System (INIS)

2006-01-01

The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. The responsibility of these researches is given to the French atomic energy commission (CEA) and to the national agency for radioactive wastes (ANDRA) who have to coordinate their works with other research organizations and industrialists. The aim of this colloquium is to make a status of the scientific knowledge gained before the implementation of the public and parliamentary debates on nuclear wastes management. This document gathers the presentations (slides) given at the colloquium and dealing with: separation/transmutation, storage and conditioning of waste packages; geologic disposal, the inter-disciplinary PACE program of the CNRS; synthesis of the researches evaluation process; general principles for a sustainable management of radioactive wastes; technical experience implemented by industrialists since 15 years; point of view of the nuclear safety authority; international context of nuclear waste management and related researches; a sociological enlightening: researches advance as seen by the public. (J.S.)

Force-detected nuclear magnetic resonance: recent advances and future challenges.

Science.gov (United States)

Poggio, M; Degen, C L

2010-08-27

We review recent efforts to detect small numbers of nuclear spins using magnetic resonance force microscopy. Magnetic resonance force microscopy (MRFM) is a scanning probe technique that relies on the mechanical measurement of the weak magnetic force between a microscopic magnet and the magnetic moments in a sample. Spurred by the recent progress in fabricating ultrasensitive force detectors, MRFM has rapidly improved its capability over the last decade. Today it boasts a spin sensitivity that surpasses conventional, inductive nuclear magnetic resonance detectors by about eight orders of magnitude. In this review we touch on the origins of this technique and focus on its recent application to nanoscale nuclear spin ensembles, in particular on the imaging of nanoscale objects with a three-dimensional (3D) spatial resolution better than 10 nm. We consider the experimental advances driving this work and highlight the underlying physical principles and limitations of the method. Finally, we discuss the challenges that must be met in order to advance the technique towards single nuclear spin sensitivity-and perhaps-to 3D microscopy of molecules with atomic resolution.

Design of an advanced human-centered supervisory system for a nuclear fuel reprocessing system

International Nuclear Information System (INIS)

Riera, B.; Lambert, M.; Martel, G.

1999-01-01

In the field of highly automated processes, our research concerns supervisory system design adapted to supervisory and default diagnosis by human operators. The interpretation of decisional human behaviour models shows that the tasks of human operators require different information, which has repercussions on the supervisory system design. We propose an advanced human-centred supervisory system (AHCSS) which is more adapted to human-beings, because it integrates new representation of the production system,(such as functional and behavioural aspects) with the use of advanced algorithms of detection and location. Based on an approach using these new concepts, and AHCSS was created for a nuclear fuel reprocessing system. (authors)

Research in JAERI on the backend of nuclear fuel cycle

International Nuclear Information System (INIS)

Maeda, Mitsuru; Takeshita, Isao

1999-01-01

Japan's policy of the backend of nuclear fuel cycle is to reprocess spent fuels and recycle recovered plutonium and uranium, under the principle of no surplus plutonium. High-level radioactive waste separated during reprocessing will be disposed of after solidification in vitrified form, followed by the storage for 30 to 50 years and finally by ultimate disposal in a deep geological formation. The role of JAERI and the effective utilization of NUCEF would become more important. The current status of JAERI's research on backend cycle is reviewed together with the future research direction with emphases on NUCEF utilization. (1) Major objectives of safety research is to develop safety criteria and establish technical bases for licensing, to improve the safety of current or near future technology and to clarify the safety margin of licensed technology. (2) The present goal of fundamental research is to show or clarify the chemical or scientific feasibility of advanced system such as for recycling minor actinides or for incinerating long-lived nuclides. (3) Supporting research for nuclear material control is also conducted mainly for international contribution to strengthened safeguards by IAEA and to frame working of international monitoring system for CTBT. (J.P.N.)

Efficiency improvement of nuclear power plant operation: the significant role of advanced nuclear fuel technologies

International Nuclear Information System (INIS)

Velde Van de, A.; Burtak, F.

2001-01-01

Due to the increased liberalisation of the power markets, nuclear power generation is being exposed to high cost reduction pressure. In this paper we highlight the role of advanced nuclear fuel technologies to reduce the fuel cycle costs and therefore increase the efficiency of nuclear power plant operation. The key factor is a more efficient utilisation of the fuel and present developments at Siemens are consequently directed at (i) further increase of batch average burnup, (ii) improvement of fuel reliability, (iii) enlargement of fuel operation margins and (iv) improvement of methods for fuel design and core analysis. As a result, the nuclear fuel cycle costs for a typical LWR have been reduced during the past decades by about US$ 35 million per year. The estimated impact of further burnup increases on the fuel cycle costs is expected to be an additional saving of US$10 - 15 million per year. Due to the fact that the fuel will operate closer to design limits, a careful approach is required when introducing advanced fuel features in reload quantities. Trust and co-operation between the fuel vendors and the utilities is a prerequisite for the common success. (authors)

CSAU (code scaling, applicability and uncertainty), a tool to prioritize advanced reactor research

International Nuclear Information System (INIS)

Wilson, G.E.; Boyack, B.E.

1990-01-01

Best Estimate computer codes have been accepted by the US Nuclear Regulatory Commission as an optional tool for performing safety analysis related to the licensing and regulation of current nuclear reactors producing commercial electrical power, providing their uncertainty is quantified. In support of this policy change, the NRC and its contractors and consultants have developed and demonstrated an uncertainty quantification methodology called CSAU. At the process level, the method is generic to any application which relies on best estimate computer code simulations to determine safe operating margins. The primary use of the CSAU methodology is to quantify safety margins for existing designs; however, the methodology can also serve an equally important role in advanced reactor research for plants not yet built. Applied early, during the period when alternate designs are being evaluated, the methodology can identify the relative importance of the sources of uncertainty in the knowledge of each plant behavior and, thereby, help prioritize the research needed to bring the new designs to fruition. This paper describes the CSAU methodology, at the generic process level, and provides the general principles whereby it may be applied to evaluations of advanced reactor designs. 9 refs., 1 fig., 1 tab

Nuclear systems of the future: international forum generation 4 and research and development projects at the Cea

International Nuclear Information System (INIS)

Carre, F.

2003-01-01

To advance nuclear energy to meet future energy needs, ten countries have agreed to develop a future generation of nuclear energy systems, known as Generation 4. A technology road map to guide the Generation 4 effort was begun. This document presents the goals for these nuclear systems and the research programs of the Cea on the gas technology, GT-MHR, VHTR and GFR and the other systems as sodium Fast Neutron reactors, supercritical water and space nuclear. (A.L.B.)

Nuclear reactor safety research in Idaho

International Nuclear Information System (INIS)

Zeile, H.J.

1983-01-01

Detailed information about the performance of nuclear reactor systems, and especially about the nuclear fuel, is vital in determining the consequences of a reactor accident. Fission products released from the fuel during accidents are the ultimate safety concern to the general public living in the vicinity of a nuclear reactor plant. Safety research conducted at the Idaho National Engineering Laboratory (INEL) in support of the U.S. Nuclear Regulatory Commission (NRC) has provided the NRC with detailed data relating to most of the postulated nuclear reactor accidents. Engineers and scientists at the INEL are now in the process of gathering data related to the most severe nuclear reactor accident - the core melt accident. This paper describes the focus of the nuclear reactor safety research at the INEL. The key results expected from the severe core damage safety research program are discussed

French experience in design, operation and revamping of nuclear research reactors, in support of advanced reactors development

International Nuclear Information System (INIS)

Barre, B.; Bergeonneau, P.; Merchie, F.; Minguet, J.L.; Rousselle, P.

1996-01-01

The French nuclear program is strongly based on the R and D work performed in the CEA nuclear research centers and particularly on the various experimental programs carried out in its research reactors in the frame of cooperative actions between the Commissariat a l'Energie Atomique (CEA), Framatome and Electricite de France (EDF). Several types of research reactors have been built by Technicatome and CEA to carry out successfully this considerable R and D work on fuels and materials, among them the socalled Materials Testing Reactors (MTR) SILOE (35 MW) and OSIRIS (70 MW) which are indeed very well suited for technological irradiations. Their simple and flexible design and the large irradiation space available around the core, the SILOE and OSIRIS reactors can be shared by several types of applications such as fuel and material testings for nuclear power plants, radioisotopes production, silicon doping and fundamental research. It is worthwhile recalling that Technicatome and CEA have also built research reactors fully dedicated to safety experimental studies, such as the CABRI, SCARABEE and PHEBUS reactors at Cadarache, and others dedicated to fundamental research such as ORPHEE (14 MW) and the Reacteur a Haut Flux -High Flux Reactor- (RHF 57 MW). This paper will present some of the most significant conceptual and design features of all these reactors as well as the main improvements brought to most of them in the last years. Based on this wide experience, CEA and Technicatome have specially designed for export a new multipurpose research reactor named SIRIUS, with two versions depending on the utilization spectrum and the power range (5 MW to 30 MW). At last, CEA has recently launched the preliminary project study of a new MTR, the Jules Horowitz Reactor, to meet the future needs of fuels and materials irradiations in the next 4 or 5 decades, in support of the French long term nuclear power program. (J.P.N.)

Recent advances in measurements of the nuclear level density

International Nuclear Information System (INIS)

John, Bency

2007-01-01

A short review of recent advances in measurements of the nuclear level density is given. First results of the inverse level density parameter - angular momentum correlation in a number of nuclei around Z∼50 shell region at an excitation energy around 0.3 MeV/nucleon are presented. Significant variations observed over and above the expected shell corrections are discussed in context of the emerging trends in microscopic calculations of the nuclear level density. (author)

Future plant of basic research for nuclear energy by university researchers

International Nuclear Information System (INIS)

Shibata, Toshikazu

1984-01-01

National Committee for Nuclear Energy Research, Japan Science Council has completed a future plan for basic nuclear energy research by university researchers. The JSC has recommended the promotion of basic research for nuclear energy based on the plan in 1983. The future plan consists of four main research fields, namely, (1) improvements of reactor safety, (2) down stream, (3) thorium fuel reactors, and (4) applications of research reactor and radioisotopes. (author)

National Nuclear Research Institute Annual Report 2013

International Nuclear Information System (INIS)

2014-01-01

The report highlights the activities of the National Nuclear Research Institute (NNRI) of the Ghana Atomic Energy Commission for the year 2013, grouped under the following headings: Centres under the institute namely Nuclear Reactors Research Centre (NRRC); Accelerator Research Centre (ARC); Engineering Services Centre (ESC); National Radioactive Waste Management Centre (NRWMC); Nuclear Chemistry and Environmental Research Centre (NCERC); Nuclear Applications Centre (NAC) and National Data Centre (NDC). (A. B.)

Advanced fuels campaign 2013 accomplishments

Energy Technology Data Exchange (ETDEWEB)

Braase, Lori [Idaho National Lab. (INL), Idaho Falls, ID (United States); Hamelin, Doug [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2013-10-01

The mission of the Advanced Fuels Campaign (AFC) is to perform Research, Development, and Demonstration (RD&D) activities for advanced fuel forms (including cladding) to enhance the performance and safety of the nation’s current and future reactors; enhance proliferation resistance of nuclear fuel; effectively utilize nuclear energy resources; and address the longer-term waste management challenges. This includes development of a state-of-the art Research and Development (R&D) infrastructure to support the use of “goal-oriented science-based approach.” In support of the Fuel Cycle Research and Development (FCRD) program, AFC is responsible for developing advanced fuels technologies to support the various fuel cycle options defined in the Department of Energy (DOE) Nuclear Energy Research and Development Roadmap, Report to Congress, April 2010. Accomplishments made during fiscal year (FY) 2013 are highlighted in this report, which focuses on completed work and results. The process details leading up to the results are not included; however, the technical contact is provided for each section.

IAEA technical meeting on nuclear data library for advanced systems - Fusion devices

International Nuclear Information System (INIS)

Forrest, R.; Mengoni, A.

2008-04-01

A Technical Meeting on 'Nuclear Data Library for Advanced Systems - Fusion Devices' was held at the IAEA Headquarters in Vienna from 31 October to 2 November 2007. The main objective of the initiative has been to define a proposal and detailed plan of activities for a Co-ordinated Research Project on this subject. Details of the discussions which took place at the meeting, including a review of the current activities in the field, a list of recommendations and a proposed timeline schedule for the CRP are summarized in this report. (author)

NRC review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Evolutionary plant designs, Chapter 1, Project No. 669

International Nuclear Information System (INIS)

1992-08-01

The staff of the US Nuclear Regulatory Commission has prepared Volume 2 (Parts 1 and 2) of a safety evaluation report (SER), ''NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Evolutionary Plant Designs,'' to document the results of its review of the Electric Power Research Institute's ''Advanced Light Water Reactor Utility Requirements Document.'' This SER gives the results of the staff's review of Volume II of the Requirements Document for evolutionary plant designs, which consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant (approximately 1300 megawatts-electric)

Nuclear safety research

International Nuclear Information System (INIS)

1996-01-01

The topics 'Large-sized PWR-NPP Safety Techniques Research',and 'The Key Techniques Research on the Safety Supervision and Control for Operation of Nuclear Installations' have been adopted as an apart of 'the National 9th five Year Programs for Tacking the Key Scientific and Technical Topics' which are organized by the State Planning Commission (SPC) and State Science and Technology Commission (SSTC) respectively, and have obtained a financial support from them. To play a better role with the limited fund, the NNSA laid special stress on selecting key sub-topics on nuclear safety, and carefully choosing units which would undertake sub-topics and signing technical contracts with them

Advanced nuclear reactors and their simulators

International Nuclear Information System (INIS)

Chaushevski, Anton; Boshevski, Tome

2003-01-01

Population growth, economy development and improvement life standard impact on continually energy needs as well as electricity. Fossil fuels have limited reserves, instability market prices and destroying environmental impacts. The hydro energy capacities highly depend on geographic and climate conditions. The nuclear fission is significant factor for covering electricity needs in this century. Reasonable capital costs, low fuel and operating expenses, environmental acceptable are some of the facts that makes the nuclear energy an attractive option especially for the developing countries. The simulators for nuclear reactors are an additional software tool in order to understand, study research and analyze the processes in nuclear reactors. (Original)

Nuclear methods in environmental and energy research

Energy Technology Data Exchange (ETDEWEB)

Vogt, J R [ed.

1980-01-01

A total of 75 papers were presented on nuclear methods for analysis of environmental and biological samples. Sessions were devoted to software and mathematical methods; nuclear methods in atmospheric and water research; nuclear and atomic methodology; nuclear methods in biology and medicine; and nuclear methods in energy research.

Nuclear methods in environmental and energy research

International Nuclear Information System (INIS)

Vogt, J.R.

1980-01-01

A total of 75 papers were presented on nuclear methods for analysis of environmental and biological samples. Sessions were devoted to software and mathematical methods; nuclear methods in atmospheric and water research; nuclear and atomic methodology; nuclear methods in biology and medicine; and nuclear methods in energy research

Cost estimate guidelines for advanced nuclear power technologies

International Nuclear Information System (INIS)

Delene, J.G.; Hudson, C.R. II.

1990-03-01

To make comparative assessments of competing technologies, consistent ground rules must be applied when developing cost estimates. This document provides a uniform set of assumptions, ground rules, and requirements that can be used in developing cost estimates for advanced nuclear power technologies. 10 refs., 8 figs., 32 tabs

Termination of past nuclear activities at the nuclear research institute

International Nuclear Information System (INIS)

Janzekovic, H.; Krizman, M.

2006-01-01

Many countries, particularly in Europe, started with nuclear programs in the fifties of the last century. As a consequence nuclear research institutes were established, among them also the Institute Jozef Stefan (IJS) in Slovenia. The nuclear activities at the IJS were related to the development of uranium ore processing technology and technologies comprising uranium oxide and hexafluoride. After very intensive period of nuclear activities the decline began step by step due to different reasons. Various approaches of the termination and decommissioning of facilities were used. The inspectors of the Slovenian Nuclear Safety Administration (SNSA), the responsible authority, started intensive activities at the IJS at the end of 2004. All together 22 research laboratories or research units were included in the inspection program and around 50 researchers of the IJS were involved into the inspection procedures. The inspection was very intensive in the laboratories and storages where past nuclear activities took place and were later on abandoned. As a result several contaminated equipments and sites in addition to around 200 unregistered sources were found. The majority of these sources is related to past nuclear activities. The inspection program related to the terminated research activities is still in progress. The IJS immediately started with the remediation activities including the development of methodology related to decontamination of radioactive liquids. The decontamination of two nuclear laboratories and three different storages of radioactive waste at its sites is in progress. Sixty of the above mentioned sources have been already stored in the Central Interim Storage for Radioactive Waste. (author)

Public Information on the Nuclear Energy and Advanced Technology Agency of Cuba

International Nuclear Information System (INIS)

Contreras Izquierdo, Marta Alicia

2007-01-01

The mission of the Nuclear Energy and Advanced Technology Agency of Cuba is the promoting and controlling of the peaceful use of nuclear energy and radiation application; additionally, they have to inform the general public about those technologies. The main of this work is to expose the methodology and results of the studies of the attitudes toward the nuclear applications of the users of the nuclear techniques

Dynamic high energy density plasma environments at the National Ignition Facility for nuclear science research

Science.gov (United States)

Cerjan, Ch J.; Bernstein, L.; Berzak Hopkins, L.; Bionta, R. M.; Bleuel, D. L.; Caggiano, J. A.; Cassata, W. S.; Brune, C. R.; Frenje, J.; Gatu-Johnson, M.; Gharibyan, N.; Grim, G.; Hagmann, Chr; Hamza, A.; Hatarik, R.; Hartouni, E. P.; Henry, E. A.; Herrmann, H.; Izumi, N.; Kalantar, D. H.; Khater, H. Y.; Kim, Y.; Kritcher, A.; Litvinov, Yu A.; Merrill, F.; Moody, K.; Neumayer, P.; Ratkiewicz, A.; Rinderknecht, H. G.; Sayre, D.; Shaughnessy, D.; Spears, B.; Stoeffl, W.; Tommasini, R.; Yeamans, Ch; Velsko, C.; Wiescher, M.; Couder, M.; Zylstra, A.; Schneider, D.

2018-03-01

The generation of dynamic high energy density plasmas in the pico- to nano-second time domain at high-energy laser facilities affords unprecedented nuclear science research possibilities. At the National Ignition Facility (NIF), the primary goal of inertial confinement fusion research has led to the synergistic development of a unique high brightness neutron source, sophisticated nuclear diagnostic instrumentation, and versatile experimental platforms. These novel experimental capabilities provide a new path to investigate nuclear processes and structural effects in the time, mass and energy density domains relevant to astrophysical phenomena in a unique terrestrial environment. Some immediate applications include neutron capture cross-section evaluation, fission fragment production, and ion energy loss measurement in electron-degenerate plasmas. More generally, the NIF conditions provide a singular environment to investigate the interplay of atomic and nuclear processes such as plasma screening effects upon thermonuclear reactivity. Achieving enhanced understanding of many of these effects will also significantly advance fusion energy research and challenge existing theoretical models.

Evolutionary developments of advanced PWR nuclear fuels and cladding materials

International Nuclear Information System (INIS)

Kim, Kyu-Tae

2013-01-01

Highlights: • PWR fuel and cladding materials development processes are provided. • Evolution of PWR advanced fuel in U.S.A. and in Korea is described. • Cutting-edge design features against grid-to-rod fretting and debris are explained. • High performance data of advanced grids, debris filters and claddings are given. -- Abstract: The evolutionary developments of advanced PWR fuels and cladding materials are explained with outstanding design features of nuclear fuel assembly components and zirconium-base cladding materials. The advanced PWR fuel and cladding materials development processes are also provided along with verification tests, which can be used as guidelines for newcomers planning to develop an advanced fuel for the first time. The up-to-date advanced fuels with the advanced cladding materials may provide a high level of economic utilization and reliable performance even under current and upcoming aggressive operating conditions. To be specific, nuclear fuel vendors may achieve high fuel burnup capability of between 45,000 and 65,000 MWD/MTU batch average, overpower thermal margin of as much as 15% and longer cycle length up to 24 months on the one hand and fuel failure rates of around 10 −6 on the other hand. However, there is still a need for better understanding of grid-to-rod fretting wear mechanisms leading to major PWR fuel defects in the world and subsequently a driving force for developing innovative spacer grid designs with zero fretting wear-induced fuel failure

25 Years of DECOVALEX - Research Advances and Lessons Learned from an International Model Comparison Initiative

Science.gov (United States)

Birkholzer, J. T.

2017-12-01

This presentation provides an overview of an international research and model comparison collaboration (DECOVALEX) for advancing the understanding and modeling of coupled thermo-hydro-mechanical-chemical (THMC) processes in geological systems. Prediction of these coupled effects is an essential part of the performance and safety assessment of geologic disposal systems for radioactive waste and spent nuclear fuel, and is also relevant for a range of other sub-surface engineering activities. DECOVALEX research activities have been supported by a large number of radioactive-waste-management organizations and regulatory authorities. Research teams from more than a dozen international partner organizations have participated in the comparative modeling evaluation of complex field and laboratory experiments in the UK, Switzerland, Japan, France and Sweden. Together, these tasks (1) have addressed a wide range of relevant issues related to engineered and natural system behavior in argillaceous, crystalline and other host rocks, (2) have yielded in-depth knowledge of coupled THM and THMC processes associated with nuclear waste repositories and wider geo-engineering applications, and (3) have advanced the capability, as well as demonstrated the suitability, of numerical simulation models for quantitative analysis.

Advanced nuclear plant control complex

International Nuclear Information System (INIS)

Scarola, K.; Jamison, S.; Manazir, R.M.; Rescorl, R.L.; Harmon, D.L.

1991-01-01

An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system which is nuclear qualified for rapid response to changes in plant parameters and a component control system which together provide a discrete monitoring and control capability at a panel in the control room. A separate data processing system, which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs and a large, overhead integrated process status overview board. The discrete indicator and alarm system and the data processing system receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accidental conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof. (author)

Progress of nuclear safety research, (2)

International Nuclear Information System (INIS)

Amano, Hiroshi; Nakamura, Hiroei; Nozawa, Masao

1981-01-01

The Japan Atomic Energy Research Institute was established in 1956 in conformity with the national policy to extensively conduct the research associated with nuclear energy. Since then, the research on nuclear energy safety has been conducted. In 1978, the Division of Reactor Safety was organized to conduct the large research programs with large scale test facilities. Thereafter, the Divisions of Reactor Safety Evaluation, Environmental Safety Research and Reactor Fuel Examination were organized successevely in the Reactor Safety Research Center. The subjects of research have ranged from the safety of nuclear reactors to that in the recycling of nuclear fuel. In this pamphlet, the activities in JAERI associated with the safety research are reported, which have been carried out in the past two years. Also the international cooperation research program in which JAERI participated is included. This pamphlet consists of two parts and in this Part 2, the environmental safety research is described. The evaluation and analysis of environmental radioactivity, the study on radioactive waste management and the studies on various subjects related to environmental safety are reported. (Kako, I.)

Advanced plant design recommendations from Cook Nuclear Plant experience

International Nuclear Information System (INIS)

Zimmerman, W.L.

1993-01-01

A project in the American Electric Power Service Corporation to review operating and maintenance experience at Cook Nuclear Plant to identify recommendations for advanced nuclear plant design is described. Recommendations so gathered in the areas of plant fluid systems, instrument and control, testing and surveillance provisions, plant layout of equipment, provisions to enhance effective maintenance, ventilation systems, radiological protection, and construction, are presented accordingly. An example for a design review checklist for effective plant operations and maintenance is suggested

Conceptual Nuclear Design Of Two Models Of Research Reactor Proposed For Vietnam

International Nuclear Information System (INIS)

Nguyen Nhi Dien; Huynh Ton Nghiem; Le Vinh Vinh; Vo Doan Hai Dang

2007-01-01

The joint study on the development of a new research reactor model for Vietnam was done. The KAERI (Korea Atomic Energy Research Institute) experts and DNRI (Dalat Nuclear Research Institute) researchers developed an advanced HANARO reactor (AHR), a 20-MW open-tank-in-pool type reactor, upward cooled and moderated by light water, reflected by heavy water and rod type fuel assemblies used. Based on the AHR model, a MTR reactor with plate fuel assemblies was developed. Computer codes named MCNP and MVP/BURN were used. Major analyses have been done for the relevant nuclear design parameters such as the neutron flux and power distributions, reactivity coefficients, control rod worth, etc. in both with clean, unperturbed core and equilibrium core condition. In case of AHR model, calculation results using MVP/BURN and MCNP codes were compared with the results using HELIOS and MCNP codes by KAERI experts and they are in a good agreement. (author)

Integrative Curriculum Development in Nuclear Education and Research Vertical Enhancement Program

International Nuclear Information System (INIS)

Egarievwe, Stephen U.; Jow, Julius O.; Edwards, Matthew E.; Montgomery, V. Trent; James, Ralph B.; Blackburn, Noel D.; Glenn, Chance M.

2015-01-01

introduction to user facilities/equipment at BNL that are used for research in room-temperature semiconductor nuclear detectors, 2) presentations on advances on this project and on wide band-gap semiconductor nuclear detectors in general, and 3) graduate students' research presentations. - Invited speakers and lectures: This brings collaborating research scientist from BNL to give talks and lectures on topics directly related to the project. Attendance includes faculty members, researchers and students throughout the university. - Faculty-students team summer research at BNL: This DOE and National Science Foundation (NSF) program help train students and faculty members in research. Faculty members go on to establish research collaborations with scientists at BNL, develop and submit research proposals to funding agencies, transform research experience at BNL to establish and enhance reach capabilities at home institution, and integrate their research into teaching through class projects and hands-on training for students. The students go on to participate in research work at BNL and at home institution, co-author research papers for conferences and technical journals, and transform their experiences into developing senior and capstone projects. - Grant proposal development: Faculty members in the NERVE program collaborate with BNL scientists to develop proposals, which often help to get external funding needed to expand and sustain the continuity of research activities and supports for student's wages and scholarships (stipends, tuition and fees). - Faculty development and mentoring: The above collaboration activities help faculty professional development. The experiences, grants, joint publications in technical journals, and supervision of student's research, including thesis and dissertation research projects, contribute greatly to faculty development. Senior scientists at BNL and senior faculty members on campus jointly mentor junior faculty members to enhance

Integrative Curriculum Development in Nuclear Education and Research Vertical Enhancement Program

Energy Technology Data Exchange (ETDEWEB)

Egarievwe, Stephen U.; Jow, Julius O.; Edwards, Matthew E.; Montgomery, V. Trent [Nuclear Engineering and Radiological Science Center, Alabama A and M University, Huntsville, AL (United States); James, Ralph B.; Blackburn, Noel D. [Nonproliferation and National Security Department, Brookhaven National Laboratory, Upton, NY (United States); Glenn, Chance M. [College of Engineering, Technology and Physical Sciences, Alabama A and M University, Huntsville, AL (United States)

2015-07-01

introduction to user facilities/equipment at BNL that are used for research in room-temperature semiconductor nuclear detectors, 2) presentations on advances on this project and on wide band-gap semiconductor nuclear detectors in general, and 3) graduate students' research presentations. - Invited speakers and lectures: This brings collaborating research scientist from BNL to give talks and lectures on topics directly related to the project. Attendance includes faculty members, researchers and students throughout the university. - Faculty-students team summer research at BNL: This DOE and National Science Foundation (NSF) program help train students and faculty members in research. Faculty members go on to establish research collaborations with scientists at BNL, develop and submit research proposals to funding agencies, transform research experience at BNL to establish and enhance reach capabilities at home institution, and integrate their research into teaching through class projects and hands-on training for students. The students go on to participate in research work at BNL and at home institution, co-author research papers for conferences and technical journals, and transform their experiences into developing senior and capstone projects. - Grant proposal development: Faculty members in the NERVE program collaborate with BNL scientists to develop proposals, which often help to get external funding needed to expand and sustain the continuity of research activities and supports for student's wages and scholarships (stipends, tuition and fees). - Faculty development and mentoring: The above collaboration activities help faculty professional development. The experiences, grants, joint publications in technical journals, and supervision of student's research, including thesis and dissertation research projects, contribute greatly to faculty development. Senior scientists at BNL and senior faculty members on campus jointly mentor junior faculty members to enhance

Review of research on advanced computational science in FY2010-2014

International Nuclear Information System (INIS)

2016-03-01

Research on advanced computational science for nuclear applications, based on 'the plan for meeting the mid-term goal of the Japan Atomic Energy Agency', has been performed at Center for Computational Science and e-Systems (CCSE), Japan Atomic Energy Agency. CCSE established the committee consisting outside experts and authorities which does research evaluation and advices for the assistance of the research and development. This report summarizes the followings. (1) Results of the R and D performed at CCSE in the period of the midterm plan (April 1st, 2010 - March 31st, 2015) (2) Results of the evaluation on the R and D by the committee in the period of the midterm plan (April 1st, 2010 - March 31st, 2015). (author)

Summaries of FY 1978 research in nuclear physics